ENDF/B-VIII.0 Beta Release Change Log ===================================== Author: D.A. Brown, NNDC, BNL Affiliation: NNDC, Brookhaven National Laboratory ENDF/B-VIII.0 Final (2 Feb 2018) -------------------------------- There were a lot of changes in this release, but they were mostly all cosmetic! CIELO Files: * n-008_O_016.endf: Make 1/v portion of capture cross section log-log interpolatable, then use LINEAR and FIXUP to ensure the total cross section is the sum of partial cross sections * n-026_Fe_056.endf: Final CIELO documentation for 56Fe, including lists of experiments used * n-094_Pu_239.endf: Corrected covariance (MF32 not overlapping with MF33 anymore) and correct zeros in distribution for (n,4n) Other Standards 2017 Files: * n-003_Li_007.endf - ensure total == sum of parts by running LINEAR and FIXUP - Fix several MF=4 and MF=5 files so that the tabulated energy range *exactly* matches that of the corresponding cross sections * n-006_C_013.endf, n-006_C_012.endf: Ensure total cross section is consistent with sum of partials using LINEAR and FIXUP * n-079_Au_197.endf: correct URR redundant cross sections for consistency, minor change to capture, elastic and total to bring into *exact* agreement with Standards evaluation Other Evaluations: * n-004_Be_009.endf - Adjust MT=1 interpolation for first 10 points to eliminate mismatch between total cross section and sum of partials - Fix first energy point mismatch between cross section and outgoing distributions in MT=16 * n-024_Cr_051.endf, n-078_Pt_190.endf: attempt to correct BR in (n,n') levels so probabilites sum to 1 * n-026_Fe_054.endf: Final documentation and covariances * n-026_Fe_057.endf, n-026_Fe_057.endf: Final documentation * n-050_Sn_126.endf: remove fission width flag * n-092_U_241.endf: Ensure that the total cross section equals the sum of partial cross sections using LINEAR and FIXUP, this fixes a major flaw in the total cross section -- a large bump near 1e-5 eV, the result of a mis-application of log-log interpolation * n-093_Np_236m1.endf: Fix the evaluation date -- I'm pretty sure the evaluation was not performed in 2027 * n-008_O_017.endf, n-011_Na_023.endf, n-018_Ar_038.endf, n-020_Ca_046.endf, n-024_Cr_051.endf, n-024_Cr_054.endf, n-027_Co_058m1.endf, n-044_Ru_105.endf, n-050_Sn_126.endf, n-092_U_230.endf, n-092_U_232.endf, n-093_Np_236m1.endf, n-081_Tl_203.endf, n-069_Tm_168.endf, n-069_Tm_169.endf, n-060_Nd_143.endf, n-069_Tm_170.endf, n-064_Gd_160.endf, n-082_Pb_204.endf, n-082_Pb_206.endf, n-033_As_074.endf, n-040_Zr_095.endf: Run LINEAR and FIXUP to ensure total cross section is sum of partials * n-010_Ne_020.endf, n-010_Ne_021.endf, n-010_Ne_022.endf, n-013_Al_026m1.endf, n-014_Si_031.endf, n-014_Si_032.endf, n-016_S_035.endf, n-017_Cl_036.endf, n-018_Ar_037.endf, n-018_Ar_039.endf, n-018_Ar_041.endf, n-020_Ca_041.endf, n-020_Ca_045.endf, n-020_Ca_047.endf, n-023_V_049.endf, n-024_Cr_051.endf, n-025_Mn_054.endf, n-026_Fe_055.endf, n-028_Ni_063.endf, n-029_Cu_064.endf, n-030_Zn_069.endf, n-031_Ga_070.endf, n-032_Ge_071.endf, n-032_Ge_075.endf, n-034_Se_075.endf, n-034_Se_081.endf, n-035_Br_080.endf, n-036_Kr_079.endf, n-036_Kr_081.endf, n-038_Sr_085.endf, n-042_Mo_093.endf, n-043_Tc_098.endf, n-044_Ru_097.endf, n-045_Rh_104.endf, n-046_Pd_103.endf, n-046_Pd_109.endf, n-047_Ag_108.endf, n-047_Ag_112.endf, n-047_Ag_113.endf, n-047_Ag_114.endf, n-047_Ag_115.endf, n-047_Ag_116.endf, n-047_Ag_117.endf, n-047_Ag_118m1.endf, n-048_Cd_107.endf, n-048_Cd_109.endf, n-049_In_114.endf, n-050_Sn_121m1.endf, n-051_Sb_122.endf, n-052_Te_121.endf, n-052_Te_121m1.endf, n-052_Te_131.endf, n-052_Te_131m1.endf, n-053_I_128.endf, n-053_I_132.endf, n-053_I_132m1.endf, n-053_I_133.endf, n-053_I_134.endf, n-054_Xe_125.endf, n-054_Xe_127.endf, n-056_Ba_131.endf, n-056_Ba_139.endf, n-058_Ce_137.endf, n-058_Ce_137m1.endf, n-060_Nd_149.endf, n-061_Pm_143.endf, n-061_Pm_144.endf, n-061_Pm_145.endf, n-061_Pm_146.endf, n-061_Pm_150.endf, n-062_Sm_145.endf, n-062_Sm_146.endf, n-064_Gd_159.endf, n-065_Tb_158.endf, n-065_Tb_161.endf, n-066_Dy_155.endf, n-066_Dy_157.endf, n-068_Er_163.endf, n-068_Er_165.endf, n-068_Er_169.endf, n-069_Tm_171.endf, n-070_Yb_169.endf, n-070_Yb_175.endf, n-072_Hf_175.endf, n-074_W_181.endf, n-074_W_185.endf, n-075_Re_186m1.endf, n-076_Os_185.endf, n-076_Os_191.endf, n-077_Ir_192.endf, n-077_Ir_194m1.endf, n-078_Pt_193.endf, n-080_Hg_197.endf, n-080_Hg_197m1.endf, n-080_Hg_203.endf, n-081_Tl_204.endf, n-082_Pb_205.endf, n-083_Bi_210m1.endf, n-084_Po_208.endf, n-084_Po_209.endf, n-084_Po_210.endf, n-094_Pu_245.endf, n-098_Cf_247.endf - Update documentation to include information about source of resonances - Ensure total cross section equals sum of partials using LINEAR and FIXUP ENDF/B-VIII.0beta7 (16 Jan 2018) -------------------------------- CIELO Files: * n-026_Fe_056.endf: Correct the resonance region covariances, adding fully correlated "background" covariance of 2% uncertainty in the Fe window region in capture and otherwise properly treating the uncertainties given in Atlas * n-092_U_235.endf, n-092_U_238.endf: Extended fission energy release energy ranges to match the cross section energy range (Thanks Wim!) * n-094_Pu_239.endf: Final version of 239Pu from LANL, with improved covariances and documentation. Additionally, the following two fixes were made: - Extended fission energy release energy ranges to match the cross section energy range (Thanks Wim!), - Fix date format in the EDATE field of MF=1 MT=451 Other Standards 2017 Files: * n-005_B_010.endf: Fix documentation for B10 changes made in Sept. 2017 * n-006_C_013.endf: Fix date format in the EDATE field of MF=1 MT=451 Other Evaluations: * n-028_Ni_058.endf Ni58 MT=103 MF=33 contained 3 sub-sections, using LB=5, 4 and 1. The LB=4 subsection appeared to contain negative variances, although after combining with other subsections the resulting matrix is fine. To avoid confusion, replace with a single LB=5 subsection containing the union grid of the three old subsections. * n-025_Mn_054.endf Remove duplicate points from outgoing energy distribution for V49 in MF6 MT5 ENDF/B-VIII.0beta6 (15 Dec 2017) -------------------------------- CIELO files: * n-008_O_016.endf: Add covariance for many channels. We suspect format problems remain. * n-026_Fe_056.endf, Three fixes: - Restore MF12 files and tweak energy ranges of MF4 files - Add covariance sections to indicate what reactions are included in lumped-sum covariance MT851 - Fix previous commit: per discussion with Gustavo and others, MT851 should be the sum of MTs 800-818 rather than 52-91 * n-092_U_235.endf: Add P(nu) data, fission energy release and covariances, including a correction to the nubar and PFNS covariance. In addition, - The PFNS energy mesh was densified to avoid "ripples" in the ratio to Maxwellian. - The high-energy tail (>10 MeV) was slightly modified (~3% at 14 MeV) to be more consistent with the description in the papers. - The PFNS thermal covariance matrix was wrong (=e71). The GMA fit with extensions was cast into a form that produces reasonable covariance matrices in different energy structures. There should be no impact on the benchmarking. * n-092_U_238.endf: Add P(nu) data, fission energy release and covariances, including a correction to the nubar and PFNS covariance. * n-094_Pu_239.endf, Two changes: - Updated covariances: capture uncertainties at higher energy and nubar uncertainty at fission spectrum energies - Added P1(mu) covariance for MT=2 * The MT 458 sections for U235 and U238 have been updated: The IFC == 1 EFR Energy of fission fragments TAB1 record contains the new total kinetic energy (TKE) evaluation from Bates and Lestone. The following values are computed to correspond to the primary evaluated data corresponding to the previous committed version. IFC == 2 ENP Energy of prompt neutrons Computed as from PFNS (MF5/MT18) * prompt nubar (MF1/MT456) IFC == 3 END Energy of delayed neutrons Computed as from DFNS (MF5/MT455) * delayed nubar (MF1/MT455) IFC == 4 ENP Energy of prompt neutrons Computed as from PFGS (MF15/MT18) * gamma multiplicity (MF12/MT18) Corresponding entries in LIST record for thermal values have also been updated. Note that uncertainties on thermal values still need to have reasonable values agreed upon and entered (based on ongoing covariance work). Other Standards 2017 Files: * n-003_Li_006.endf: Supposed to be the beta5 version, with covariances, but was misplaced. * n-005_B_010.endf: Fix gap in (n,el) covariance * n-006_C_012.endf: Revised from Hale & Paris: natC evaluation restored from 20-150 MeV. Also, correct energy range of capture cross section so matches outgoing gamma line energy range * n-006_C_013.endf: Corrected covariance data (was previously in 12C, not here) Other Evaluations: * n-000_n_001.endf: Extend evaluation to 50 MeV * n-026_Fe_054.endf: Tweak starting energies of tables to be consistent with multiplicities and cross sections for several reactions * n-026_Fe_057.endf, Two fixes: - Restore MF12 energies to correct values - Correct the channel L values so that parity is conserved * n-026_Fe_058.endf: Restore MF12 energies to correct values from beta4.1 * n-029_Cu_063.endf, Three fixes: - Fix MF32 MT151 spin group headers - Fix MT63 sum of gamma branchings in MF12 - Correct covariance matrix CONT records in MF32 for LRF=7 resonances * n-029_Cu_065.endf: Correct covariance matrix CONT records in MF32 for LRF=7 resonances * n-076_Os_191.endf: Fix first section of MF=40 MT=4 in Os191. It should refer to production of the ground state rather than 1st excited * Correct covariance matrix CONT records in MF32 for LRF=7 resonances for n-074_W_182.endf, n-074_W_183.endf, n-074_W_184.endf, n-074_W_186.endf * Update ZAP and IZAP in MF=8, 10 and 40 for sub-actinide fission. Per recent ENDF format update, ZAP = -1 indicates the total fission cross section. Impacts n-074_W_182.endf, n-074_W_183.endf, n-074_W_184.endf, n-074_W_186.endf, n-076_Os_191.endf, n-077_Ir_192.endf, n-078_Pt_190.endf, n-078_Pt_191.endf, n-078_Pt_192.endf, n-078_Pt_193.endf, n-078_Pt_194.endf, n-078_Pt_195.endf, n-078_Pt_196.endf, n-078_Pt_197.endf, n-078_Pt_198.endf, n-080_Hg_203.endf, n-081_Tl_204.endf, n-082_Pb_205.endf, n-084_Po_208.endf, and n-084_Po_210.endf * Making changes to a handful of isotopes that failed to process through NJOY's GROUPR module. Each of these files has an inconsistency in the MF/MT=6/5 LIP data. When there is more than 1 excited state, the LIP value must be incremented. For each of these, the LIP value was 0,2,3,.... The LIP=1 value was skipped over, thus causing NJOY to fail because it couldn't find the correct nuclide. Additionally, fix MF=8 MT=4 sections for several isotopes, removing an incorrectly identified isomeric state. MF=8 MT=5 had the correct set of isomers, causing a mismatch between MT=4 and 5. Impacted: n-036_Kr_081.endf, n-042_Mo_093.endf, n-077_Ir_192.endf, n-078_Pt_193.endf, n-078_Pt_195.endf, and n-078_Pt_197.endf ENDF/B-VIII.0beta5 (2 Oct 2017) ------------------------------- CIELO files: * n-001_H_001.endf: Covariances added * n-008_O_016.endf: Covariances added * n-026_Fe_056.endf: Covariances added * n-092_U_235.endf (Corresponds to IAEA u235ib46o28t6DNcnu5ef0STz5): Corrected PFNS covariance from D. Neudecker * n-092_U_238.endf (orresponds to IAEA version u238ib58lrlFsfaST4n): ** Covariances added ** Latest U238 multiplicity and PFGS spectra from Ionel Stetcu. These correspond to the plots and tables in the ENDF/B-VIII.0 'big paper' revision 272. * n-094_Pu_239.endf ** Marco Pigni took the covariance file (MF=32) from the JEFF-3.2 library and modified by minor corrections such as the last digits of the resonance energy parameters that did not match those ones in file 2. The covariance file is coupled to the resonance evaluation extracted in the frame of the WPEC/SG34 working group NEA/NSC/WPEC/DOC(2014)447. The file 32 also contains the uncertainty on the scattering radius (about 1.8%) that is almost double than one estimated in the ATLAS. Although this uncertainty seems overestimated, the file 32 was kept as originally released in the JEFF-3.2 for consistency. ** Latest U238 multiplicity and PFGS spectra from Ionel Stetcu. These correspond to the plots and tables in the ENDF/B-VIII.0 'big paper' revision 272. * The U235, U238 and Pu239 components of fission energy release (MT458) have been updated. The total average fission fragment kinetic energy [EFR] is given as tabular data using IFC 1. These are evaluated data by Bates and Lestone as described in the ENDF/B-VIII.0 'big paper'. The total average prompt fission neutron energy [ENP], total average delayed fission neutron energy, [END] and total average prompt fission gamma energy [EGP] are given as tabular data using IFC 2, 3 and 4, respectively, where the values are computed to be self-consistent with the corresponding emission distribution data. More specifically, the tabular data are: LDRV == 2, IFC == 1 evaluated TKE data LDRV == 1, IFC == 2 from PFNS (MF5/MT18 or equivalent) * prompt nubar (MF1/MT456) LDRV == 1, IFC == 3 from DFNS (MF5/MT455) * delayed nubar (MF1/MT455) LDRV == 1, IFC == 4 from PFGS (MF15/MT18) * gamma multiplicity (MF12/MT18) The computed data correspond to the last revision of the evaluations before this update, that is U235 MF1 MT458 IFC 2,3,4 are computed from r1333 U238 MF1 MT458 IFC 2,3,4 are computed from r1333 Pu239 MF1 MT458 IFC 2,3,4 are computed from r1329 Other Standards 2017 Files: * n-005_B_010.endf ** Added covariances, including first pass at high energy extension to the covariance, based on the ENDF/B-VII.1 ** For n + B10 -> t + (Be8 -> 2a), MF=6 gives an explicit distribution for the triton, then uses LAW=4 (recoil) for the two alphas. Recoil doesn't make sense in a breakup reaction (unless a distribution was assigned to one alpha and the other one treated as recoiling from that). For now use LAW=0 (unknown) instead. * n-006_C_012.endf: Added covariances Other Evaluations: * n-001_H_002.endf: Modified MF33, MT2 in the lowest energy bin to have a solid physical limit for (n,tot) and (n,n). In the new version submitted to beta5, the uncertainty of total and elastic cross sections are the same, = +/- 1.5%, at 1.0e-5 eV < E < 1.0e+5 eV (lowest energy bin), because sig(n,g) <<< sig(n,tot) for H-2 ; the correlation matrix based on MF33, MT2 is kept unchanged (so the non-diagonal elements cov(1,i), i >= 2, are re-scaled). * n-002_He_004.endf: Adjust documentation * n-025_Mn_055.endf: Adjust documentation * n-026_Fe_054.endf ** Extend file to 150 MeV ** Add dosimetry reactions * n-026_Fe_057.endf: Extend file to 150 MeV * n-026_Fe_058.endf ** Tweak energy range of inelastic angular distributions to match cross section data ** Extend file to 150 MeV * n-045_Rh_103.endf ** In the thermal range the uncertainty for capture was given as 0.034. The Atlas value is 143.5 +/- 1.5, or an uncertainty of 0.01045. The covariance matrix was changed accordingly. ** Fix bound level total width so that it equals the sum of partials * n-061_Pm_147.endf For Pm147 the relative uncertainty for capture in the RI range was 0.25. The Atlas value is: 2064 +/- 100, or 0.048 relative. The value in the covariance matrix was changed to give this result. * n-062_Sm_149.endf In the thermal range the uncertainty for capture was given as 0.05. The Atlas value is 4014 +/- 600, or an uncertainty of 0.0149. The covariance matrix was changed accordingly. * n-062_Sm_151.endf In the thermal range the uncertainty for capture was given as 0.07. The Atlas value is 15170 +/- 300, or an uncertainty of 0.0197. The covariance matrix was changed accordingly. * n-063_Eu_155.endf In the thermal range the uncertainty for capture was given as 0.05. The Atlas value is 3950 +/- 125, or an uncertainty of 0.0316. The covariance matrix was changed accordingly. * n-065_Tb_161.endf Change the name of the nuclide in the endf file to be consistent with the nuclide. * n-072_Hf_174.endf RQ Wright's tweak to bound level to get better agreement with experimental data * Remove problematic distributions for heavy residuals, replace with unknown distributions (MF=6 LAW=6). ** In Mn54, problem distribution was for outgoing V49 in MT=24 ** In Pm145, problem was for Nd145 in MT=103 ** In Os191, problem was for W186 in MT=24 * Fix various format issues in new evaluations. ** C13: format date ** Ar37 & 40: MF2/MF32 mismatch, fix NM in MF4 ** Ca45 & 47: MF2/MF32 mismatch, fix NM ** V49: Incorrect LFS in MF8/10, MF2/32 mismatch ** Cr51, Mn54, Fe55: NM, MF2/32 mismatch ** Ni63, Ge71: MF2/32 mismatch ** Ge75: Incorrect LFS in MF8/10 ** Se75: Fix MF4 NM ** Br80: Incorrect LFS in MF8/10 ** Kr81: NM, MF2/32 mismatch, incorrect LFS and XLFS1 in MF40 ** Sr85: Incorrect LFS in MF8/10 ** Mo93: NM, MF2/32 mismatch, incorrect LFS and XLFS1 in MF40 ** Tc98: NM, MF3/MF12 energy level mismatch for MT75, MF2/32 mismatch ** Ru97: NM, MF2/32 mismatch ** Rh104, Pd108, Ag108: Incorrect LFS in MF8/10 ** Cd109: NM, MF2/32 mismatch ** Sn121m1: MF2/32 mismatch ** Sb122, I133, Xe125, Xe127, Ba131, Ce137: fix LFS in MF 8/10 ** Pm144, Pm145, Pm146, Sm145: Fix NM in MF4, MF2/32 mismatch ** Tb158: Fix NM, fix LFS in MF 8/10, MF2/32 mismatch ** Tb161: Wrong ZA in several places (65160.99 instead of 65161), MF2/32 mismatch ** Er163: fix LFS in MF 8/10 ** Tm171, Yb175: MF2/32 mismatch ** W181: fix LFS in MF 8/10, MF2/32 mismatch ** W185: mass inconsistency in MF2, MF2/32 mismatch, fix LFS in MF 8/10 ** Os185: MF2/32 mismatch ** Os191: MF2/32 mismatch, missing NM in MF4, incorrect LFS in MF40 ** Ir192: masses inconsistent in MF2, MF2/32 mismatch, missing NM, MF40 LFS ** Ir194m1: MF2/32 mismatch ** Pt190, Pt191, Pt192: missing NM, MF2/32 mismatch ** Pt193: missing NM, MF2/32 mismatch, incorrect LFS MF40 ** Pt194, Pt195: masses inconsistent in MF2, MF2/32 mismatch ** Pt196, Pt197: NM, MF2/32 mismatch ** Pt198: MF2 masses inconsistent, missing NM, MF2/32 mismatch ** Hg197m1: fix NM ** Hg203: NM, MF2/32 mismatch ** Tl204: NM, MF2/32 mismatch ** Pb205: MF2 masses inconsistent, NM, MF2/32 mismatch ** Bi210m1: MF2/32 mismatch ** Po208: NM, MF2/32 mismatch ** Po209: MF2 masses inconsistent, MF2/32 mismatch ** Po210: NM, MF2/32 mismatch ** Pu245, Cf247: Fix AWR in MF4 MT18 ENDF/B-VIII.0beta4.1 (2 Sep 2017) --------------------------------- CIELO fixes: * n-008_O_016.endf: ** Remove line numbers, and remove duplicate points near the start of MF3 MT1 ** MF33 MT800 contains a section claiming to be a cross-term with MT107. However, the matrix is symmetric and the file contains no MT107 covariance, leading me to assume that this section is purely for MT800 * n-026_Fe_056.endf: "final" CIELO mean values, not including IRDFF cross section merge * n-092_U_235.endf: Revised CIELO 235U with modified fission cross section and nubar. Corresponds to IAEA version u235ib46o28t6DNcnu5ef0STz. * n-092_U_238.endf: Final version of CIELO 238U sans covariance data and PFGS. Corresponds to IAEA version u238ib58lrlFsfaST4h. * n-094_Pu_239.endf: update header; make fission Q values agree with fission energy release Big, non-CIELO changes: * Remove elemental Carbon (n-006_C_000.endf) now that we have 12C and 13C evaluations * n-001_H_002.endf: IAEA/CNL change to 2H: replace elastic scattering angular distribution with that from JEFF-3.3T Many fixes made during the 2017 Hackathon: * Americium: ** n-095_Am_242m1.endf make two nearly degenerate levels slightly less degenerate ** n-095_Am_244m1.endf, n-095_Am_244.endf: ensure angular distribution is positive * Arsenic: ** n-033_As_073.endf, n-033_As_074.endf: Fix interpolation of MT 1,2,102 background cross sections in transition from RRR to URR & fast also fix NMOD & the MT107 Q value in 73As * Copper: ** n-029_Cu_065.endf: Added one space to Cu-65 TPID. This fixes issue #1086. ** n-029_Cu_065.endf: remove extra character on the first line * Curium: ** n-096_Cm_248.endf: remove duplicate point in angular distribution and tweak energy value of MT57 level ** n-096_Cm_243.endf: nudge one (n,n') energy level so it's no longer a duplicate level (MT=54) nudge one incident energy in the (n,el) angular distribution so that it's no longer a duplicate * Erbium: ** n-068_Er_167.endf, n-068_Er_168.endf, n-068_Er_170.endf, n-068_Er_166.endf: Use LEGEND to convert MT=51-54 angular distributions to pointwise, then make them positive definite ** n-068_Er_162.endf, n-068_Er_170.endf: Fix various evaluations so that cross sections and distributions begin/end at same point * Gadolinium: ** n-064_Gd_152.endf: negative elastic scattering at low energies fixed by moving the low-energy (n,alpha) cross section to the total. ** n-064_Gd_154.endf: Nudge the energy of one of the resonance slightly to avoid having two resonances with identical resonance parameters. This makes it impossible to find the correct resonance for the covariance data. * Halfnium: ** n-072_Hf_174.endf: comment section added ** n-072_Hf_174.endf, n-072_Hf_176.endf, n-072_Hf_177.endf, n-072_Hf_178.endf, n-072_Hf_179.endf, n-072_Hf_180.endf: comment section modified * Iron: ** n-026_Fe_054.endf: turn off resonance shift factor, RECENT & FUDGE ignore it ** n-026_Fe_057.endf: Several small fixes to resonances: *** Fix Q value of MT 51 particle pairs to match MT 51 cross section *** Correct all channel parities, they were all multiplied by -1 (parity isn't used in cross section of angular distribution calcs, so this does nothing) *** Correct the SHF parameter to match the ENDF manual *** Correct the JPi=1+ spin group's potential scattering contribution by adding MT=2,51 channels *** Correct the JPi=2+ spin group's potential scattering contribution by adding an MT=51 channel ** n-026_Fe_054.endf, n-026_Fe_056.endf, n-026_Fe_058.endf: Fixed MF12/MF3 gamma energies in favor of MF3. Some now have 8 sig. digits in MF12 * Tin: ** n-050_Sn_122.endf: fix interpolation in MT=1,2,102 ** n-050_Sn_124.endf: add back bound resonance at -176 eV (it was lost in revision 685) set interpolation flag to lin-lin (INT=2) for MT=1,2,102 cross sections to eliminate log(0) error spotted by FIZCON * Tungsten: ** n-074_W_180.endf, n-074_W_182.endf, n-074_W_183.endf: Fix incorrect excited state indices in MF 8/10 for W isotopes. Closes tracker #788 ** n-074_W_183.endf: Fix the channel spin parity flag in File 32 for W183. This was already fixed in File 2 ** n-074_W_180.endf: Additional fix to W180 (MF=8 vs MF=10 level mismatch) * n-002_He_003.endf: Change interpolation on total cross section to log-log. Closes tracker #1082 * n-004_Be_009.endf: change TPID on first line * n-005_B_010.endf: ** make angular distribution positive definate ** n-005_B_010.endf uses LR=22 in MT 700 to indicate the breakup of Be8 into two alphas. According to the ENDF manual (page 19 of the 2012 edition), LRs 22-36 are provided for compatibility with ENDF/B-V. LR=1 is preferred for new evaluations. Since all products are explicitly listed in MF 6, this simply changes the LR flag to LR=1. * n-006_C_013.endf: eliminate degenerate energies in angular distributions and cross sections * n-017_Cl_035.endf: Close tracker 1066: Fix the SHF value from -1 to 0 for Cl35 * n-018_Ar_040.endf: negative cross section at 978 keV fixed by increasing BG slightly * n-028_Ni_060.endf: double value at end of resonance region in (n,el) were not actually double, leading to negative cross section once resonances were reconstructed * n-041_Nb_093.endf: Fixed outgoing ZA error in 93Nb and AWR incorrect in resonance file * n-043_Tc_098.endf: Fix the j values for File 32 in the URR to be the same as given in File 2 for 98Tc * n-058_Ce_136.endf: back-ground problem in the elastic and (n,alpha) cross sections fixed. * n-066_Dy_160.endf: MF3 MT3 removed and Fix negative elastic cross section * n-067_Ho_166m1.endf: tweak energy of level in MF12, MT811 to match level energy in MF3 MT811 * n-092_U_241.endf: Change MT=3 gammas in U241. Previously the gamma production cross section increased linearly from 0 at 1e-5 eV to non-zero 100 keV, replacing that with a step function at 100 keV. Low-energy capture and fission gammas are given elsewhere, so it seems that MT=3 was double-counting. * n-098_Cf_249.endf: Fix degenerate 8th level in MT58, the level energy should have been 2.1 keV higher. This fix applied to MF3, 6, and 33 * Fixed MF12/MF3 gamma energies in favor of MF3. Some now have 8 sig. digits in MF12: n-013_Al_026m1.endf, n-018_Ar_037.endf, n-018_Ar_041.endf, n-020_Ca_047.endf, n-022_Ti_049.endf, n-023_V_049.endf, n-025_Mn_054.endf, n-028_Ni_063.endf, n-032_Ge_075.endf, n-034_Se_075.endf, n-040_Zr_094.endf, n-044_Ru_097.endf, n-045_Rh_104.endf, n-047_Ag_116.endf, n-049_In_114.endf, n-051_Sb_122.endf, n-054_Xe_127.endf, n-055_Cs_133.endf, n-061_Pm_143.endf, n-062_Sm_145.endf, n-062_Sm_152.endf, n-063_Eu_153.endf, n-064_Gd_156.endf, n-066_Dy_156.endf, n-066_Dy_163.endf, n-066_Dy_164.endf, n-068_Er_163.endf, n-072_Hf_175.endf, n-074_W_181.endf, n-078_Pt_193.endf, n-078_Pt_197.endf, n-080_Hg_196.endf, n-080_Hg_202.endf, n-081_Tl_204.endf, n-092_U_235.endf, n-092_U_238.endf, n-058_Ce_137.endf, n-028_Ni_063.endf, n-032_Ge_071.endf, n-033_As_075.endf, n-046_Pd_103.endf, n-047_Ag_108.endf, n-047_Ag_118m1.endf, n-048_Cd_107.endf, n-052_Te_121.endf, n-058_Ce_137m1.endf, n-066_Dy_155.endf, n-068_Er_169.endf, n-070_Yb_175.endf, n-072_Hf_175.endf, n-048_Cd_107.endf, n-052_Te_121m1.endf, n-052_Te_131m1.endf, n-083_Bi_210m1.endf, n-016_S_035.endf, n-061_Pm_146.endf, n-065_Tb_158.endf, n-069_Tm_171.endf, n-070_Yb_169.endf, n-074_W_185.endf, n-075_Re_186m1.endf, n-076_Os_185.endf, n-077_Ir_194m1.endf, n-084_Po_209.endf, n-032_Ge_072.endf, n-032_Ge_073.endf * URR covariance fixes: n-017_Cl_036.endf, n-025_Mn_054.endf, n-047_Ag_118m1.endf, n-061_Pm_144.endf, n-061_Pm_146.endf, n-077_Ir_192.endf, n-077_Ir_194m1.endf, n-083_Bi_210m1.endf, n-084_Po_208.endf, n-065_Tb_158.endf, n-075_Re_186m1.endf, n-081_Tl_204.endf, n-084_Po_210.endf, n-017_Cl_036.endf, n-018_Ar_037.endf, n-069_Tm_171.endf, n-081_Tl_204.endf. If URR has non-zero values for all l and j in the covariance data, update the j to be in line with the values in file 2. Otherwise delete the URR covariance data. * Fix NMOD, NLIB, NVER on many files, prepare headers for ENDF/B-VIII.0 Add evaluations as part of project to adopt TENDL evaluation & supplement those with EMPIRE calculations: * New files: n-084_Po_209.endf, n-014_Si_031.endf, n-014_Si_032.endf, n-016_S_035.endf, n-017_Cl_036.endf, n-018_Ar_039.endf, n-020_Ca_041.endf, n-013_Al_026m1.endf, n-023_V_049.endf, n-028_Ni_063.endf, n-029_Cu_064.endf, n-030_Zn_069.endf, n-031_Ga_070.endf, n-032_Ge_071.endf, n-032_Ge_075.endf, n-034_Se_081.endf, n-035_Br_080.endf, n-036_Kr_079.endf, n-038_Sr_085.endf, n-045_Rh_104.endf, n-046_Pd_103.endf, n-046_Pd_109.endf, n-047_Ag_108.endf, n-047_Ag_112.endf, n-047_Ag_113.endf, n-047_Ag_114.endf, n-047_Ag_115.endf, n-047_Ag_116.endf, n-047_Ag_117.endf, n-047_Ag_118m1.endf, n-048_Cd_107.endf, n-049_In_114.endf, n-050_Sn_121m1.endf, n-051_Sb_122.endf, n-052_Te_121.endf, n-052_Te_121m1.endf, n-052_Te_131.endf, n-052_Te_131m1.endf, n-053_I_128.endf, n-053_I_132.endf, n-053_I_132m1.endf, n-053_I_133.endf, n-053_I_134.endf, n-054_Xe_125.endf, n-054_Xe_127.endf, n-056_Ba_131.endf, n-056_Ba_139.endf, n-058_Ce_137.endf, n-058_Ce_137m1.endf, n-060_Nd_149.endf, n-061_Pm_146.endf, n-061_Pm_150.endf, n-062_Sm_146.endf, n-064_Gd_159.endf, n-065_Tb_158.endf, n-065_Tb_161.endf, n-066_Dy_155.endf, n-066_Dy_157.endf, n-068_Er_163.endf, n-068_Er_165.endf, n-068_Er_169.endf, n-069_Tm_171.endf, n-070_Yb_169.endf, n-070_Yb_175.endf, n-072_Hf_175.endf, n-074_W_181.endf, n-074_W_185.endf, n-075_Re_186m1.endf, n-076_Os_185.endf, n-077_Ir_194m1.endf, n-080_Hg_197.endf n-080_Hg_197m1.endf, n-083_Bi_210m1.endf, n-094_Pu_245.endf, n-098_Cf_247.endf, n-010_Ne_020.endf, n-010_Ne_021.endf, n-010_Ne_022.endf, n-018_Ar_037.endf, n-018_Ar_041.endf, n-020_Ca_045.endf, n-020_Ca_047.endf, n-024_Cr_051.endf, n-025_Mn_054.endf, n-026_Fe_055.endf, n-034_Se_075.endf, n-036_Kr_081.endf, n-042_Mo_093.endf, n-043_Tc_098.endf, n-044_Ru_097.endf, n-048_Cd_109.endf, n-061_Pm_143.endf, n-061_Pm_144.endf, n-061_Pm_145.endf, n-062_Sm_145.endf, n-076_Os_191.endf, n-077_Ir_192.endf, n-080_Hg_203.endf, n-084_Po_208.endf, n-081_Tl_204.endf, n-082_Pb_205.endf, n-084_Po_210.endf * n-098_Cf_247.endf: Add fission nubars, PFNS and fission neutron angular distributions from nearest even-odd nucleus (249Cf) * n-094_Pu_245.endf: Add fission nubar, PFNS and angular distribution from 243Pu, nearest odd-even nucleus * n-080_Hg_197.endf, n-080_Hg_197m1.endf: Fix issues with new Hg197 evaluations: assign MAT numbers, set LDRV=0, fix level index issues in MF 8/10, fix ELIS and LIS for the m1 evaluation * Fix mismatches between MF=8 / MF=10 in several new evaluations: n-036_Kr_081.endf, n-042_Mo_093.endf, n-076_Os_191.endf, n-077_Ir_192.endf, n-078_Pt_193.endf, n-052_Te_121m1.endf, n-053_I_132.endf, n-053_I_132m1.endf, n-052_Te_131.endf, n-052_Te_131m1.endf, n-052_Te_121.endf, n-052_Te_121m1.endf, n-047_Ag_118m1.endf, n-050_Sn_121m1.endf, n-058_Ce_137m1.endf, n-075_Re_186m1.endf, n-077_Ir_194m1.endf, n-083_Bi_210m1.endf * n-013_Al_026m1.endf: Fix issues with new Al26_m1 evaluation: MF=1 needs excited state energy, plus should indicate unstable nucleus - Remove non-zero values from reserved field in MF=4 - ensure level indices are right in MF=8 and 10 * Add correct MAT numbers to many new evaluations * Fix LDRV flag in many new evaluations (LDRV should be 0 unless the file is derived, application-specific data) Added & corrected Pt evaluations from TENDL: * New files: n-078_Pt_190.endf, n-078_Pt_191.endf, n-078_Pt_192.endf, n-078_Pt_194.endf, n-078_Pt_195.endf, n-078_Pt_196.endf, n-078_Pt_197.endf, n-078_Pt_198.endf, n-078_Pt_193.endf * n-078_Pt_194.endf, n-078_Pt_198.endf: Fix mismatch between width in File 2 and File32 to allow to get covariance data in RR. The uncertainty for the widht has been adjusted to keep the same relative value. * n-078_Pt_192.endf New File 2 and File 32 evaluations from Dimitri Rochman for Pt192 to makes sure that File 2 and File 32 resonances are in sync. * n-078_Pt_195.endf: Fix metastable indices in Pt195. MF6 lists the 7th excited state (259 keV, t1/2 = 4 days) as metastable. MF8 has that state but also lists the 1st excited state (98 keV, t1/2 = 170ps), incorrectly labeled as the ground state. * n-078_Pt_197.endf: Like Pt195, 197 includes two metastables in MF8 but only one in MF6. Fix up LIP and LIS flags * n-078_Pt_190.endf, n-078_Pt_192.endf, n-078_Pt_194.endf, n-078_Pt_196.endf, n-078_Pt_198.endf Remove the URR covariance data from some of the Pt isotopes as the J valuse between File 32 and File 2 do not agree and the average resonance parameeters for one of the J value in File 32 are 0. Added & corrected Ne evaluations from TENDL: * New files: n-010_Ne_020.endf, n-010_Ne_021.endf, n-010_Ne_022.endf * n-010_Ne_022.endf: Update the File 32 width for some resonances to the one given in File 2. The uncertainty for those width is recalculated to give the same relative uncertainty. For Ne22 URR covariance was removed. * n-010_Ne_020.endf: make MF32 resonance parameters match MF2; toss out off-diagonal terms in Ne20: they try to assign to matrix elements out of range! Other assorted fixes: * n-094_Pu_240.endf: Several fixes: ** Fix resonance energies in MF=32 to match MF=2. ** Change the engy range of the incident energies for the chi covariance matrix (File 35) in Pu240 as per Denise Neudecker's recommendation. ** Change MF10 energy from 4.298000+4 to 4.297984+4 for consistency with MF3/MT51 * n-022_Ti_048.endf: adjust the Q values of the MT=58 cross section to be consistent with ENSDF and the MF=12 data. * n-073_Ta_180.endf, n-073_Ta_181.endf, n-075_Re_185.endf, n-075_Re_187.endf Fix minor format issues in LLNL Ta and Re evaluations: MF=12 used LP=0 meaning 'origin of photons not designated', but the origin is given in field ES on the same line. ENDF/B-VIII.0beta4 (28 Feb 2017) -------------------------------- CIELO evaluations: * n-001_H_001.endf: New version with standards cross section, tested in-house at LANL. Documentation and file-33 not updated yet * n-026_Fe_056.endf (IAEA file fe56ib20w.endf): Slightly revised version from previous, capture backround around 25 keV slightly reduced, but not zeroed. MACS(30 keV) = 13.97 mb, somewhat higher than KaDoNiS recommendation, but consistent with several MACS(30 keV) data sets. This file also includes a few minor fixes in the fast region: - Fixed missing branching ratios for 56Fe and 57Fe levels in discrete-level file for Fe56. This should not affect any cross sections, only gammas. - Main changes were in order to improve agreement of high-energy (between ~ 50 and 150 MeV) alpha production with exp. data. This was done by identifying which nuclei contribute the most to alpha emissions at 150 MeV and then fitted the level-density and alpha-emission tuning parameters for those nuclei. This fit was done through senstivity matrix calculations and Kalman. - Calculations were done with Rev. 4825 of EMPIRE. * n-092_U_235.endf: 3 Changes 1 revision r1060: (IAEA u235ib36o28p6DNcnu5ef0STi) nu-bar below 75 eV increased by 0.05% to compensate the loss of reactivity due to the new LANL hydrogen (STD 2016). U-235 resonance parameters were changed (ORNL RP file 28p) to decrease the slope of HST benchmarks vs ATLF. Comments need updating 2 revision r1071: (IAEA u235ib36o28t6DNcnu5ef0STm) (comments need update) Small changes to resonance parameters for consistency with Standards_2016 resonance fission integrals from 100 eV up to 1 keV, and a small change to nu-bar (from 1-27 eV) to compensate the change in gradient with ATLF in HST benchmarks. 3 revision r1071: (IAEA u235ib36o28t6DNcnu5ef0STs) The Standards were modified slightly and they affected benchmark performance. The U-238(n,f) cross section below the Standards region was defined on a finer mesh, so it was decided to adopt it (previously the ENDF/B-VI.8 was taken). The cross sections were made consistent with the new Standards in the "Standards" region, as well as in the region of "recommended" cross sections (pointwise or group-wise). This meant that U-235 and U-238 evaluations needed additional tuning. Small changes to nu-bar were made. The new PFNS of U-235 by D. Neudecker are included, as well as the fission gamma data from Stetcu (LANL). * n-092_U_238.endf; new version of U-238: (IAEA u238ib54lrlFsfaST4d) The Standards were modified slightly and they affected benchmark performance. The U-238(n,f) cross section below the Standards region was defined on a finer mesh, so it was decided to adopt it (previously the ENDF/B-VI.8 was taken). The cross sections were made consistent with the new Standards in the "Standards" region, as well as in the region of "recommended" cross sections (pointwise or group-wise). This meant that U-235 and U-238 evaluations needed additional tuning. Small changes to nu-bar were made. The new PFNS of U-235 by D. Neudecker are included, as well as the fission gamma data from Stetcu (LANL). * n-094_Pu_239.endf (IAEA File pu239e80b4_5_corDN (as submitted by D. Neudecker on 22 February)) The file was made consistent with Standards_2017, including a correction to the PFNS for Einc = 17.5, 20 and 30 MeV (were missing). In addition, the prompt nu-bar from 0.9 MeV to 6 MeV was adjusted. Use a 1.002 factor at 1.0 MeV, with a linear ramp down to a 1.000 factor a 6.0 Mev. Make a corresponding change to total nu-bar. - This seemingly arbitrary change is easily accommodated by the spread in experimental data and yields better calculated PMF eigenvalues. - A more rigorous re-analysis of the existing experimental database remains a future task. Other evaluations using Standards 2017 data: * n-003_Li_006.endf: New R-matrix analysis from G. Hale. Results from a new R-matrix analysis of the 7Li system, done up to 4 MeV neutron energy, were included in this evaluation for MF=3, MT=1,2,105. The results were obtained by fitting the (n,t) cross section that resulted from the 2016 GMA standards evaluation, along with data from other reactions in the 7Li sytem. * n-005_B_010.endf: New R-matrix analysis from G. Hale: 1. Standard (n,a) cross sections were fitted with R-matrix analy- sis at energies up to 1 MeV. 2. (n,a) cross sections were modified at higher energies to agree with data of Schrack (n,a1) and Gioginis (n,a). 3. Total cross section was modified at higher energies to better agree with data of Wasson (200 m) and of Abfalterer. 4. Capture cross section (3-102) was modified to agree with recent data from Firestone (thermal) and of Igashira (keVs). 5. Kornilov data for the (n,t) reaction were used in the R- matrix fit below 1 MeV; cross section (3-700) was unchanged at energies above 1 MeV. 6. Elastic neutron scattering angular distributions (4-2) changed below 1 MeV. Angular distributions were also changed at energies below 1 MeV for the (n,a0) (6-800) and (n,a1) (6-801) reactions, and added for the (n,t) (6-700) reaction. 7. MT 605 (n,p') from the 5th excited state at 6263.3 keV does not decay by pair production. The LR flag, previously set to 40 was changed to 0. * n-079_Au_197.endf (IAEA filename: au197STD-2017-final-11Feb17-vp.endf): New version of JEFF-3.3's Au-197 file with the Standards_2017 implemented, including - Extended the URR up to 2 keV and agreement with the LSD benchmark was additionally improved through an alternative use of the statistical and standard infinitely dilute capture cross section in the three regions 2-3.75 keV, 3.75-11.75 keV, and 11.75-100 keV, by keeping continuity. - Below 2 keV all resolved resonance parameters were reevaluated based on measurements at n_TOF and GELINA. - This file is essentually ENDF/B-VII.1 above the resonance region but includes updated covariances. Other notable changes: * n-017_Cl_035.endf: This commit is motivated by the incorrect mass of the (n,p) particle-pair for which the mass of 35Cl was reported instead of the correct mass of 35S. The mass of the elastic particle-pair was also made consistent to that one reported in file 3. - Changes on the masses are based on the atomic mass evaluation 2012. 1) correction of the mass for elastic particle-pair 35Cl (MT=2): 2) correction of the mass for the (n,g) particle-pair 36Cl (MT=102) 3) correction of the mass for the (n,p) particle-pair 35S (MT=600) - Additional correction on the charge number for the elastic particle-pair: the charge number was set to zero instead of Z=17. Luckily, this had no impact on the cross sections because for the elastic particle-pair the penetrability factors are independent from the charge number Z. - Changes 1),2) and 3) generated negligible changes on the cross sections when the cross sections for all reaction channels were reconstructed from file 2. - Note: the Q-value calculated with the masses of Atomic Mass Evaluation 2012 is Q=615.0234 keV. This is slightly different from that reported in the current file Q= 615.2200 keV. * n-017_Cl_037.endf; MF=3, MT=102 #had 2 interpolation regions. There was only 1 interpolation region in MF=3, MT=1. MF=3 MT=1 has been corrected to have 2 interpolation regions. We believe that this did not change any of the transport calculations because in AMPX and NJOY the total cross section is calculated from the sum of the partials and therefore the error in MF=3 MT=1 should never have entered transport calculations. * n-026_Fe_054.endf: Merged fast file from CIELO Iron project rev. 412 (Fast/fe54-CIELO.endf) with resonances from CIELO Iron project rev. 379 of Full/fe54-CIELO.endf. This merged file has (n,p) and (n,2n) replaced by IRDFF. Added fluctuations in fast region by replacing (n,total) by JENDL-4.0 between 1.036 MeV and 7.25 MeV. Reconstructed elastic for consistency. * n-026_Fe_057.endf; Merged fast file from CIELO Iron project rev. 397 (Fast/fe57-CIELO.endf) with resonances from CIELO Iron project rev. 311 of Full/fe57-CIELO.endf. * n-026_Fe_058.endf: Merged fast file from CIELO Iron project rev. 396 (Fast/fe58-CIELO.endf) with resonances from CIELO Iron project rev.244 of Full/fe58-CIELO.endf. Rebuild with URR set for self-shielding only * n-029_Cu_063.endf: Resonance Parameter Covariance Matrix (file 32) has been added for the resonance parameters from the beta2 version. RPCM has been calculated using the retroactive covariance matrix methodology of SAMMY and the unrealistically small uncertainties on the resonance parameters have been increased to calculate cross section uncertainties on the order of several percent for a 44 group cross section covariance matrix using a constant flux. * n-029_Cu_065.endf: Resonance Parameter Covariance Matrix (file 32) has been added for the resonance parameters from the beta2 version. RPCM has been calculated using the retroactive covariance matrix methodology of SAMMY and the unrealistically small uncertainties on the resonance parameters have been increased to calculate cross section uncertainties on the order of several percent for a 44 group cross section covariance matrix using a constant flux. * n-033_As_074.endf: Set the URR use for self-shielding calculations only to avoid double counting of average cross section * n-094_Pu_240.endf (IAEA pu240e80b31c): Changed to improve MCF benchmarks and measured reaction rates (PROFIL). - Fission cross section updated: Replaced by Tovesson 2009 data from 5.7keV to 40 keV (URR), Weston 40keV - 190keV. - Capture cross section taken from ENDF/B-VII.0 (=ENDF-B/VI.8), with an additional 2% reduction above 42 keV to improve Pu240ng measured reaction rates (PROFIL). Also replaced Pu-240(n,g) above URR with ENDF/B-Vi.8, which is Weston’s evaluation, who also made the only measurement in this energy range. - Elastic cross section taken from ENDF/B-VII.0 (=ENDF-B/VI.8). * n-095_Am_241.endf: add an isotropic MF4/MT18 section to go with the PFNS ENDF/B-VIII.0beta3.1 (19 Jan 2017) ---------------------------------- CIELO evaluations: * n-008_O_016.endf: new evaluation of capture cross section based on the R-matrix (up to 2 MeV) and the DSD model in CoH3 (2 - 30 MeV). Also 2 minor bugs were also fixed: - MF4 MT2, odd number of Legendre coefficient at 0.1 eV - different threshold energy of (n,alpha) in MF14 * n-026_Fe_054.endf: Several changes: - Add in roughly 64 resonances from G. Giubrone’s thesis “Neutron capture measurement of 54Fe and 57Fe at CERN n_TOF”, University of Valencia (2014), noted in Atlas evaluation but missing from IRSN evaluation - Add high energy capture background to the RRR to account for missing p- & d-wave resonances * n-026_Fe_056.endf: New CIELO revision for Fe56, corresponding to IAEA version fe56ib19v. Major change: The elastic angular distributions in the resolved resonance range are taken from resolution-broadened Perey data. Above the resonance range up to 2.5 MeV the angular distributions correspond to re-fitted Kinney data with some adjustments based on the comparison with Perey data in the overlapping region. In the range 2.5-4.0 MeV the angular distributions are taken from Smith (1973). Above 2.5 MeV the angular distributions are from the Empire calculation. * n-092_U_235.endf: CIELO evaluations for 235,238U including new standards evaluation and PFNS * n-092_U_238.endf: CIELO evaluations for 235,238U including new standards evaluation and PFNS * n-094_Pu_239.endf: New CIELO evaluation. It contains: - The final prompt fission gamma rays from I. Stetcu - T. Kawano’s results for gamma-ray production from all channels other than fission - (n,2n) tweak near the threshold and below 8 MeV - (n,f) cross section adjusted to the final standards released on Dec. 14, 2016 It does NOT contain the P(nu;Einc) evaluation yet, as LANL decided it is better to keep those for beta5 instead. New or mostly new evaluations: * n-004_Be_009.endf: New LANL 9Be evaluation * n-006_C_013.endf: New 13C evaluation from LANL * n-079_Au_197.endf: Proposed evaluation: based on ENDF/B-VII.1 cross sections in the fast energy range and resonance parameters evaluated at IRMM * n-092_U_233.endf: Replace with CIELO project version: JENDL-4.0 + updated resonances to get thermal cross sections + LANL PFNS Other notable changes: * Reverted n-029_Cu_063.endf and n-029_Cu_065.endf to their beta2 versions due to poor performance of the beta3 version in critical assembly benchmarks * n-094_Pu_240.endf: - Adjusted the negative (bound) levels of the Resolved Resonance Region (RRR) evaluation (File 2) with evaluation code SAMMY (Larson) to better match the thermal cross section values found in the Atlas of Neutron Resonances (Mughabghab). - The Resonance parameter covariance matrix (File 32) was adjusted accordingly to preserve the relative uncertainty on the cross section of the original evaluation of Derrien et. al. In File 32, non-zero uncertainty is reported for zero fission widths of the 2 spin groups associated with p-wave resonances. 12 of those variances were negative and were changed to be the corresponding positive value. * n-095_Am_241.endf: The (n,n'), (n,2n), (n,3n), (n,4n), and capture cross sections updated based on a new CoH3 calculation. The MF=6 sections corresponding to the new cross sections are also provided including complete photon production information. * n-095_Am_243.endf: - The prompt fission spectrum replaced by JENDL-4. - Stop the RRR at 50 keV rather than 250 keV and extend the URR down to 50 keV. There were no resonances above 250 keV to provide a background for the resonances from 80-250 keV, so we had a strange dip in the reconstructed cross section. The URR extension does a reasonable job matching the average cross section. This resolves tracker item #1043. * n-099_Es_254m1.endf: Correct the ZA in MF=31 data, was set to 9.925410+4 * Remove sign from channel spin in new LRF=7 evaluations (per CSEWG 2016 format discussion): n-020_Ca_040.endf, n-029_Cu_063.endf, n-029_Cu_065.endf, n-074_W_183.endf ENDF/B-VIII.0beta3 (1 Nov 2016) ------------------------------- CIELO evaluations: * n-026_Fe_054.endf: New Fe54 evaluation with the following: 1) IRSN resonances up to 1.036 MeV 2) New EMPIRE calculation from 1.036 MeV - 150 MeV 3) (n,2n), (n,p) and (n,a) cross sections taken from IRDFF, partial reactions scaled to match these totals * n-026_Fe_056.endf: IAEA file fe56ib18b, IAEA-BNL Collaboration for CIELO: - Resolved resonance range up to 850 keV basically from JENDL-4.0 - The resonance energy at 766.7 kev was corrected. - The background near 800 keV was reduced by 50 percent. - Artificial "background" was added to capture around 24.5 keV, since capture in the hole of the elastic seems to be low and is HIGHLY SENSITIVE to many benchmarks. It was stipulated thet the broad dip in this energy region is caused by inappropriately placed bound states. The adjusted capture cross section now follows the 1/v behaviour. - The total cross section above the resonance range was taken from JEFF-3.2 because it is consistent with the Berthold measurements on Fe-nat. The contribution of the minor isotopes is taken into account. - The capture cross sections above 860 keV were taken from the RPI data presented by Y. Danon at the ND2016 Conference. - JEFF-3.2 contains inelastic cross sections measured by Dupont et al., but the authors discovered normalisation problems and the results were never published. New measurements were performed by Negret, but with a lower resolution. The Dupont and Negret data were binned over a suitable energy mesh. A piecewise linear scaling parameter was constructed to adjust Dupont data such that they agree on average with the Negret data. It was also found that the energy calibration of Negret data did not match the resonances of the total cross section. A correction was made to the energy scale which amounted to 2.5 keV at 1.8 MeV. Inelastic cross sections between 0.85e6 and 3.5e6 eV are taken from JEFF-3.2. - The elastic cross section is defined as the difference between the total and the remaining partial cross sections. By resolution-broadening of the elastic cross section to 0.3 percent, good agreement is observed with the measured Kinney data. - The elastic angular distributions in the resolved resonance range were reconstructed from the resonance parameters. The Legendre moments were resolution-broadened with a resolution function of constant width of 1 keV. For most applications the resolution-broadened Legendre coefficients are sufficient, but the user still has the option to reconstruct detailed distributions from the resonance parameters. Above the resonance range up to 4 MeV the angular distributions were taken from JEFF-3.2 because they accurately follow the Kinney data (with a correction for the minor isotopes). - The P2 Legendre coefficients of elastic scattering were increased linearl, starting with 0 at 0.3 MeV, peaking to 0.7 at 0.85 MeV and ending with 0 at 1.5 MeV. - Similarly, the P4 Legendre coefficients of elastic scattering were increased linearly, starting with 0 at 0.5 MeV, peaking to 0.2 at 0.85 MeV and ending with 0 at 1.5 MeV. - At higher energies all cross sections, angular distributions and spectra are taken from EMPIRE calculation, which was tuned to reproduce the important reaction channels and radionuclide production data. * n-026_Fe_057.endf: Fe57 revised with new EMPIRE calculation for fast region * n-094_Pu_239.endf: October 31, 2016 Major update... *** MF1, MT456/452: Prompt and total neutron multiplicities are replaced by the original results from the statistical analysis of experimental data by P.G. Young using the GLUCS code. The modification introduced in the fast energy range for the average prompt neutron multiplicity in the ENDF/B-VII library is removed. The average total neutron multiplicity is adjusted accordingly. *** MF3, MT18: The fission cross section evaluated as part of the 2016 standard evaluation is adopted here above 40 keV and up to 20 MeV. *** MF3, MT102: The capture cross section follows the recent modification of ENDF/B-VII.1 above 30 keV to better match recent DANCE data by Mosby et al. [Mo16] up to 0.7 MeV, where it switches to Kawano's CoH3 calculations [Ka16] up to 3.7 MeV. For now (to be replaced), from 3.7 to 20 MeV, it then matches the previous ENDF/B-VII.1 evaluation. *** MF5, MT18: The PFNS was obtained from an evaluation by Neudecker et al. [Ne16] extending the original Los Alamos model to include the effects of emission anisotropy and different fragment temperatures, as well as to properly account for multi-chance fission evaporation and pre-equilibrium neutron spectra. The thermal PFNS was obtained by averaging the ENDF/B-VII.1 PFNS with a slightly modified PFNS by Romano. [Mo16] S. Mosby et al, private communication, publication for Phys. Rev. C in preparation. [Ka16] T. Kawano, private communication. [Ne16] D. Neudecker, P. Talou, T. Kawano, A.C. Kahler, M.E. Rising and M.C. White, EPJ Web of Conferences 111, 05004 (2016). New or mostly new evaluations: * n-017_Cl_035.endf capture cross sections above 1.2 MeV recalculated with CoH3, and the total and elastic scattering cross sections were re-adjusted. * n-017_Cl_037.endf capture cross sections above 1.2 MeV recalculated with CoH3, and the total and elastic scattering cross sections were re-adjusted. * n-027_Co_059.endf: T. Kawano's re-evaluation of fast region, using CoH3 * n-029_Cu_063.endf: ORNL + LANL Evaluation merged at 300 keV. Resonance parameter covariance matrix has been added. * n-029_Cu_065.endf: ORNL + LANL Evaluation merged at 300 keV. Resonance parameter covariance matrix has been added. * n-033_As_073.endf: T. Kawano's revised 73As evaluation using outgoing distributions generated by CoH3 * n-033_As_074.endf; New evaluation using CoH. Cross sections were matched to old evaluation so now new distributions and cross sections are internally consistant * n-036_Kr_078.endf high energy part replaced by CoH3 calculations; (n,3n) section removed * n-052_Te_132.endf Cross sections above resonance range updated by CoH3 calculations. * n-054_Xe_124.endf update high energy part with CoH3 * n-072_Hf_174.endf new evaluation above the unresolved resonance range * n-072_Hf_176.endf new evaluation based on CoH3 calculation above resonance region * n-072_Hf_177.endf new evaluation above resonance range * n-072_Hf_178.endf new evaluation above resonance range * n-072_Hf_179.endf Cross sections and energy spectra above the resonance range updated * n-072_Hf_180.endf final commit of Hf isotopes Other notable changes: * n-004_Be_007.endf: EXTENSION FROM 8.1 to 20 MeV maximum neutron energy: Cross sections for total, elastic, (n,p) and (n,a) extended to 20 MeV by rescaling the results of a defaults TALYS 1.6 calculation (without pre-equilibrium) to match the previous curves at 14 MeV. Ian Thompson. Jun 8, 2016 * n-021_Sc_045.endf: The resonance energy boundary fixed to match the pointwise cross sections. Set (n,p) cross sections zero below 96.94 keV. Reconstruct the total cross sections. * n-038_Sr_088.endf: Minor resonance region fix related to tracker #1025. * n-039_Y_089.endf Changed Q value for MF=3, MT=107 in order to fix discrepancy pointed out by PSYCHE. * n-040_Zr_090.endf: Minor resonance region fix related to tracker #1025. * n-040_Zr_091.endf: Minor resonance region fix related to tracker #1025; Restore ENDF/B-VII.1 cross sections for capture, elastic and total in the URR, set the URR data for self-shielding calculations only * n-040_Zr_094.endf Fix "hole" in the elastic, total and capture cross sections by extending the fast region cross sections down to the top of the RRR, resolving tracker item [#1014]; Minor resonance region fix related to tracker #1025. * n-040_Zr_096.endf extend the capture, total and elastic cross section down to the top of the RRR, resolving tracker item [#1013] * n-041_Nb_093.endf resonance parameters updated * n-042_Mo_095.endf: (n,el) Legendre angular moments were reconstructed from angular distributions and then matched onto EMPIRE calculations at higher energies * n-045_Rh_105.endf Convert to MLBW * n-050_Sn_120.endf: 50 keV data points in total, elastic, and capture removed * n-054_Xe_123.endf total, elastic, and capture cross sections at 10^-5 eV given by considering the 1/v shape in capture. * n-054_Xe_135.endf Convert 135Xe's sole SLBW resonance to MLBW; Fix minor formatting problems * n-061_Pm_148m1.endf; Fix J of lone resonance; Convert the sole resonance to MLBW; Fix minor formatting problems * n-062_Sm_144.endf URR energies fixed to make sure all points are inside URR (not required). Total cross sections reconstructed from all partial cross sections. * n-063_Eu_154.endf The first resonance energy changed into 0.188 eV. * n-073_Ta_180.endf Pointwise values for MF=3 at 1e-5 eV fixed by Ian Thompson, LLNL * n-092_U_239.endf: Resonance and URR regions now include 3+ resonance spins as well as the 2+ previous spins. Points above 10 keV patched to merge on these. Specifications adjusted at URR lower boundary. I.J. Thompson, LLNL, Oct 2016 * n-092_U_240.endf Changing the resonance flag for the U-240 file from Single-Level Breit-Wigner to Multi-Level Breit Wigner (LRF=1 to LRF=2). * n-092_U_241.endf Change resonance spins in U-241 from 0.5 to 1.0.; add documentation, make MLBW * n-094_Pu_243.endf Changed resonance spins from 3.5 and 2.5 to 4.0 and 3.0 respectively. Also changed to LRF=2 (MLBW). * n-095_Am_243.endf: Minor resonance region fix related to tracker #1025. * Adopted the prompt nubar proposed by R.Q.Wright added, and recalculated the total nubar in following evaluations: n-093_Np_236.endf, n-093_Np_238.endf, n-094_Pu_243.endf, n-094_Pu_244.endf, n-094_Pu_246.endf, n-096_Cm_241.endf, n-096_Cm_242.endf, n-096_Cm_244.endf, n-096_Cm_246.endf, n-096_Cm_247.endf, n-096_Cm_248.endf, n-096_Cm_249.endf, n-096_Cm_250.endf, n-097_Bk_245.endf, n-097_Bk_246.endf, n-097_Bk_247.endf, n-097_Bk_248.endf, n-097_Bk_249.endf, n-097_Bk_250.endf, n-098_Cf_246.endf, n-098_Cf_248.endf, n-098_Cf_249.endf, n-098_Cf_250.endf, n-098_Cf_251.endf, n-098_Cf_252.endf, n-098_Cf_253.endf, n-098_Cf_254.endf, n-099_Es_251.endf, n-099_Es_252.endf, n-099_Es_253.endf, n-099_Es_254.endf, n-099_Es_255.endf, n-100_Fm_255.endf ENDF/B-VIII.0beta2 (19 Aug 2016) -------------------------------- CIELO evaluations: * n-026_Fe_054.endf: Revised 54Fe from the CIELO project. This evaluation includes revised resonance region from IRSN up to 1.2 MeV in the LRF=7 format, EMPIRE calculation for fast region and capture cross section tuned to match average resonance cross section. DSD capture was added above the resonance region. * n-026_Fe_056.endf: Revised 56Fe from the CIELO project. This evaluation includes revised resonance region from IRSN up to 850 keV in the LRF=7 format, elastic and inelastic cross sections and angular distributions from beta1 and EMPIRE calculation for the remainder of the fast region. * n-092_U_235.endf: CIELO 235U file u235ib18o23g6cnu5ef1 from `https://www-nds.iaea.org/CIELO/`, product of an ORNL, LANL and IAEA collaboration. Major components of evaluation: - Empire calculation 'ib18' (capture at upper limit of Jandel) - Improved fit of Kammerdiener ddx at 14 MeV - Resonance parameters ORNL version 'o23' - PFNS - GMA fit at thermal, Talou above - Prompt nu-bar evaluated by V. Pronyaev, based on Reed data from C00-3058-39, normalized to thermal value of 2,41161. Simon data were measured rel.to 252Cf(sf) normalized at 10-27 eV on Reed's data (10-Jan-2016) The dip in the data around 30 eV was suppressed. Thermal value was increased to 2.414 below 0.2 eV (g6cnu5e) - Fission data (except PFNS) from ENDF/B-VII.1 - Delayed nu-bar and spectra from ENDF/B-VII.1 * n-092_U_238.endf: CIELO 238U file ib46rlFs from `https://www-nds.iaea.org/CIELO/`, product of an IRMM, LANL and IAEA collaboration. General information: - Empire ib46 calculation. - Resonance file IRMM URR from 'u8GelinaRR.end' New resolved/unresolved resonance evaluation from IRMM - Major cross sections in the UR range conform to Standards joint fit. - PFNS by Talou. Note: 'ib46'='ib45' with (n,3n) exclusive and cleaner formatting. This revision includes a fix to unit conversion problem on 2nd-order coefficients from MT458 fission energy release. * n-094_Pu_239.endf: CIELO file pu239lanlmbc2v from `https://www-nds.iaea.org/CIELO/`, product of an IRMM, LANL and IAEA collaboration. General information: - Fix unit conversion problem on 2nd-order coefficients from MT458 fission energy release. - Changed to LSSF=1 in URR - Replace capture (mf3,mt102) above 30 keV with new modification from Chadwick to follow Mosby data. Modify elastic (mf3,mt2) to preserve total x/s. - Replace "Romano" thermal pfns tweak with an alternate tweak that is the average of the Romano+original e71 thermal pfns. Other notable changes: * n-004_Be_007.endf: Fix outgoing alpha multiplicities for n+Be7->a+a (two alpha products are listed, so each should have multiplicity=1) * n-006_C_012.endf: 2 fixes: 1. ZAI in the first isotope in the resonance region was set to 6000, not 6012 2. For the (n,n') levels, QM should have been all set to 0.0 MeV, QI should have been set to the -(level energy) * n-006_C_013.endf: Revised 13C evaluation from M. Paris and G. Hale. This new evaluation of the n+13C reactions is based on a six-channel R-matrix analysis of reactions in the 14C system at energies up to 20 MeV. Data included were total cross sections and angular distributions up to 5 MeV. A fair fit is obtained to the 3676 data points included. * n-020_Ca_040.endf: Ca-40 resolved resonance evaluation, performed in energy range from 1e-5 eV to 1.5 MeV with the SAMMY code in ORNL. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process in the energy region up to 1.5 MeV. The RML formalism (LRF=7) was used for the resonance parameters and the formalism (LCOMP=1) for the covariance matrix. Thermal cross sections (for reconstructed cross sections at T=293.6 K) are: Total 3.075396 b, (n,g) 2.662938 b, (n,el) 0.409977 b, and (n,a) 0.002481 b. * n-029_Cu_063.endf, n-029_Cu_065.endf from ORNL, LANL collaboration: - Updated resolved resonance region evaluation for cu63 and cu65. The high energy capture data normalization has been corrected and the resonance parameters refitted to eliminate the dip of the capture cross section at the end of the resolved resonance region. Angular distribution data for elastic scattering for incident neutron energies between 1e-5 eV and 300 keV should be calculated directly from the resonance parameters in File 2 using the Blatt and Biedenharn formalism, if the capabilities of the processing code permit. Otherwise, the coefficients of the expansion of the angular distribution in the Legendre moments have been provided in File 4 on a reduced energy grid sufficient to maintain comparable performance in neutron transport calculations. - Collaboration work is on going with LANL to smooth the transition from the resolved resonance region (File 2) to the high energy region (File 3) in both angle integrated cross sections and distributions of elastic scattering with a schedule completion date of Nov, 2016. The upper resonance boundary was temporally changed to 100keV, and LANL evaluation concatenated - The covariance part of the evaluation has been removed just for the beta2 testing version. New resonance parameter covariance matrices will be added once the synchronization of the resonance region with the high energy region is complete. * n-033_As_073.endf: New evaluation from T.Kawano, including some fixes: - Make sure the number of gammas is equal in corresponding MF12 and MF14 files Get BR's of some MF12 levels to sum up to 1.0 - First (n,p) excited state in MF=3 had wrong energy. Note: this file is missing the second (n,p) state in MF=3, but has it in MF=12 so MF=3 & MF=12 are out of sync - Fix mismatches between excited state energies for As73 (n,p*) reactions. * n-093_Np_236m1.endf: Fix unit conversion problem on 2nd-order coefficients from MT458 fission energy release. ENDF/B-VIII.0beta1 (25 Apr 2016) -------------------------------- * Replacing Be-7 with evaluation that goes up to 20 MeV. * Improved documentation in n-092_U_238.endf * Hale & Paris's (LANL) isotopic C evaluations (12C, 13C) * CIELO 235U file from IAEA * Final 57Fe from CIELO iron project (rev. 246 of CIELO Iron project) * Final 54Fe from CIELO Iron project (rev. 246 of CIELO Iron project) * Final CIELO 56Fe before WPEC meetings (rev. 246 of CIELO Iron project) * Revert prompt and total nu-bar (MF1 MT456, 452) to ENDF/B-VII.1 values for ENDF/B-VIII beta1 release. This allows for establishing a baseline for future improvements. * Bug fixes in several files (n-008_O_016.endf, n-006_C_013.endf, n-092_U_235.endf, n-007_N_015.endf, n-026_Fe_054.endf) ENDF/B-VIII.0beta0 (8 Apr 2016) ------------------------------- CIELO evaluations: * n-001_H_001.endf: ** Comment section modified slightly to avoid confusions (T. Kawano). ** Covariance data replaced by Hale's high fidelity evaluation (T. Kawano). * n-008_O_016.endf: CIELO 16O file from G. Hale, et al. (LANL) * n-026_Fe_056.endf: CIELO 56Fe file from BNL, IAEA and CNDC * n-092_U_235.endf: CIELO 235U file. From IAEA, LANL, ... ** Added a delayed neutron multiplicity covariance matrix (MF=31,MT=455) using a least-square fit of available data. The total neutron multiplicity covariance matrix (MF=31,MT=452) is now inferred from the prompt (MT=456) and delayed (MT=455). It fixes a problem observed with very large uncertainties in the total neutron multiplicity in the thermal and URR regions. (P. Talou) * n-092_U_238.endf: CIELO 238U file. Documentation needs updating. From IAEA, LANL, ... * n-094_Pu_239.endf: CIELO 239Pu evaluation. From IAEA, LANL, ORNL, IRSN, ... ** Fixed a small error in prompt fission neutron spectrum (MF5,MT18), where the 16.0 MeV incident neutron energy is replaced by 17.5 MeV. (P. Talou) ** Fixed zero uncertainty in prompt nu-bar covariance matrix (MF31,MT456) at first energy point. The same fix was applied to the covariance matrix for the total nu-bar (MF31,MT452). (P. Talou) ** Updated evaluation in the resolved range for 239-Pu (L. Luiz et al., ORNL) Features of the evaluation: 1. One single set of resonances parameters covering the energy range from 0.00001 eV to 2.5 keV. 2. SAMMY (Reich-Moore) analysis of the experimental data led to a set of resonance parameters that fit well the experimental data and improves benchmark calculations in the thermal region. 3. Integral quantities such as K1 and eta (nu*capture/fission) were the two major indicators on how to fix the problem with thermal benchmark results. 4. Experimental data used in the previous Pu-239 resonance were used. The experimental data were well represented with the new resonance evaluation. New full evaluations: * Add neutron evaluation (yes, that's neutron as a target) * Add 18O evaluation from ROSFUND library, fix total width of 4.09 MeV resonance (was off by factor of 10 from sum of GN and GG), adjust lower limit of MT102 (capture) to eliminate a whole in the reconstructed capture cross section and adjust the total cross section to account for this modification * Add minor Fe isotopes from the CIELO collaboration (54Fe, 57Fe and 58Fe). New fast regions in all from EMPIRE calculations. New (currently undocumented) resonance regions in all: ** 54Fe, new Atlas values, in Reich-Moore format ** 57Fe, new Atlas values, in LRF=7 format, Reich-Moore approximation ** 58Fe, new evaluation from Moxon * Add Dy isotopes from JENDL-4.0+, filling in holes in ENDF (n-066_Dy_154.endf, n-066_Dy_159.endf) * Add Yb isotopes from JENDL-4.0+, Yb was not present in ENDF before (n-070_Yb_168.endf, n-070_Yb_170.endf, n-070_Yb_171.endf, n-070_Yb_172.endf, n-070_Yb_173.endf, n-070_Yb_174.endf, n-070_Yb_176.endf) * Add Hf isotopes from JENDL-4.0+, filling in holes in ENDF (n-072_Hf_181.endf, n-072_Hf_182.endf) * Adding Os isotopes from JENDL-4.0+, there was no Os in ENDF before (n-076_Os_184.endf, n-076_Os_186.endf, n-076_Os_187.endf, n-076_Os_188.endf, n-076_Os_189.endf, n-076_Os_190.endf, n-076_Os_192.endf) * New Np236 metastable evaluation, performed at LANL in Jan. 2012. New resonance region evaluations: * n-029_Cu_063.endf 29-Cu- 63 ORNL, MIT Resonance Evaluation Including Covariance and Angular Distribution of Elastic Scattering V. Sobes, L. C. Leal, K. Guber, G. Arbanas, D. Wiarda, B. Forget Resolved resonance parameter evaluation for Cu-63 was done with the computer code SAMMY. The following data were used in the SAMMY analysis. Reference | Energy (eV) | Facility | Measurement --------------|-------------------|----------|------------ Pandey et al. | 32 - 185 000 | ORELA | Trans. 78m Pandey et al. | 1 000 - 1 400 000 | ORELA | Trans. 78m Guber et al. | 100 - 90 000 | GELINA | Capt. 58m Guber et al. | 100 - 300 000 | GELINA | Capt. 58m Sobes et al. | 0.01 - 0.1 | MITR | Trans. 1.2m The MITR transmission measurements were important for determining the shape and the uncertainty of the thermal cross section. A set of resonance parameter describing the experimental data was obtained. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process. The upper energy boundary of the resonance region of Cu-63 was extended from 99.5 keV to 300 keV. Angular distribution data for elastic scattering for incident neutron energies between 1e-5 eV and 300 keV were generated directely from the new resonance parameters in File 2 on a fine energy grid. The new elastic scattering angular distribution data gives a much more detailed treatment of the angular distribution than previous evaluations. * n-029_Cu_065.endf 29-Cu- 65 ORNL, MIT Resonance Evaluation Including Covariance and Angular Distribution of Elastic Scattering V. Sobes, L. C. Leal, K. Guber, G. Arbanas, D. Wiarda, B. Forget Resolved resonance parameter evaluation for Cu-65 was done with the computer code SAMMY. The following data were used in the SAMMY analysis. Reference | Energy (eV) | Facility | Measurement --------------|-------------------|----------|------------ Pandey et al. | 32 - 185 000 | ORELA | Trans. 78m Pandey et al. | 1 000 - 1 400 000 | ORELA | Trans. 78m Guber et al. | 100 - 90 000 | GELINA | Capt. 58m Guber et al. | 100 - 300 000 | GELINA | Capt. 58m Sobes et al. | 0.01 - 0.1 | MITR | Trans. 1.2m The MITR transmission measurements were important for determining the shape and the uncertainty of the thermal cross section. A set of resonance parameter describing the experimental data was obtained. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process. The upper energy boundary of the resonance region of Cu-65 was extended from 99.5 keV to 300 keV. Angular distribution data for elastic scattering for incident neutron energies between 1e-5 eV and 300 keV were generated directely from the new resonance parameters in File 2 on a fine energy grid. The new elastic scattering angular distribution data gives a much more detailed treatment of the angular distribution than previous evaluations. * n-074_W_182.endf 74-W- 182 ORNL Resonance Evaluation Including Covariance (ORNL AUG 2014) L. Leal, M. Pigni, K. Guber, D. Wiarda, and G. Arbanas W-182 resolved resonance parameter evaluation was done in the energy range form 1e-5 eV to 10 keV with the SAMMY code[ref1]. Capture and transmission measurements for enriched W-182 and natural tungsten were used in the evaluation. The measurements were done at the Oak Ridge Linear Accelerator (ORELA)[ref2] and at the Geel Linear Accelerator (GELINA), Belgium[ref3]. Neutron transmission and capture data were measured in the energy range from 20 eV to 10 keV. Thermal cross section[ref4] data available in the EXFOR library were also used in the evaluation. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process in the energy region 1e-5 eV-10 keV. The RML formalist (LRF=7) was used for the resonance parameters and the compact formalism (LCOMP=2) for the covariance matrix. Thermal cross section and uncertainty calculated with SAMMY and the PUFF codes are compared with the values listed in the ATLAS of Neutron Resoances in the table below. Also shown is the capture resonance integral, Coherent scattering length and the effective radius R'. Cross Section ORNL (b) Atlas (b) ------------- -------- --------- Total 29.18 +/- 0.40 - Capt 20.31 +/- 0.64 19.90 +/- 0.30 Scat 8.87 +/- 0.28 8.84 +/- 0.30 Capture Res. Int. 618.41 +/- 0.17 600.00 +/- 60.0 R' 7.64 fm 8.3 +/- 0.2 fm b_coher 7.11 fm 7.04 +/- 0.04 fm Average cross section and related uncertainties calculated in energy group 0.0253 eV - 0.3 eV are listed in the table below. Cross Section Average Value (b) ------------- ----------------- Total 29.54 +/- 0.38 (1.3%) Capt 20.70 +/- 0.61 (2.9%) Scat 8.84 +/- 0.28 (3.2%) [ref 1] N. M. Larson,"Updated Users' Guide for SAMMY," Oak Ridge National Laboratory report ORNL/TM-9179/R6 (2003). [ref 2] K. Guber, private communication (2012). [ref 3] C. Lampoudis, K. Guber, S. Kopecky, et al., J. Korean Phys. Soc. 59, 1860 (2010). [ref 4] S. J. Friesenhahn, E. Haddad, F.H. Froehner, et al., Nucl. Sci. Eng. 26, 487 (1966). * n-074_W_183.endf: 74-W- 183 ORNL Resonance Evaluation Including Covariance (ORNL AUG 2014) M. Pigni, L. Leal, K. Guber, D. Wiarda, and G. Arbanas W-183 resolved resonance parameter evaluation was done in the energy range form 1e-5 eV to 5 keV with the SAMMY code[ref1]. Capture and transmission measurements for enriched W-183 and natural tungsten were used in the evaluation. The measurements were done at the Oak Ridge Linear Accelerator (ORELA)[ref2] and at the Geel Linear Accelerator (GELINA), Belgium[ref3]. Neutron transmission and capture data were measured in the energy range from 20 eV to 5 keV. Thermal cross section[ref4] data available in the EXFOR library were also used in the evaluation. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process in the energy region 1e-5 eV-5 keV. The RML formalist (LRF=7) was used for the resonance parameters and the compact formalism (LCOMP=2) for the covariance matrix. Thermal cross section and uncertainty calculated with SAMMY and the PUFF codes are compared with the values listed in the ATLAS of Neutron Resoances in the table below. Also shown is the capture resonance integral, Coherent scattering length and the effective radius R'. Cross Section ORNL (b) Atlas (b) ------------- -------- --------- Total 15.56 +/- 0.50 - Capt 9.87 +/- 0.53 10.4 +/- 0.2 Scat 5.69 +/- 0.11 2.4 +/- 0.6 Capture Res. Int. 360.82 +/- 19.30 355.0 +/- 30.0 R' 7.9789 fm 8.1 +/- 0.1 fm b_coher 6.4702 fm 6.59 +/- 0.04 fm b_incoh -0.4330 fm - Average cross section and related uncertainties calculated in energy group 0.0253 eV - 0.3 eV are listed in the table below. Cross Section Average Value (b) ------------- ----------------- Total 15.13 +/- 0.48 (3.2%) Capt 9.45 +/- 0.51 (5.4%) Scat 5.67 +/- 0.11 (2.0%) [ref 1] N. M. Larson,"Updated Users' Guide for SAMMY," Oak Ridge National Laboratory report ORNL/TM-9179/R6 (2003). [ref 2] K. Guber, private communication (2012). [ref 3] C. Lampoudis, K. Guber, S. Kopecky, et al., J. Korean Phys. Soc. 59, 1860 (2010). [ref 4] S. J. Friesenhahn, E. Haddad, F.H. Froehner, et al., Nucl. Sci. Eng. 26, 487 (1966). * n-074_W_184.endf: 74-W- 184 ORNL Resonance Evaluation Including Covariance (ORNL AUG 2014) L. Leal, M. Pigni, K. Guber, D. Wiarda, and G. Arbanas W-184 resolved resonance parameter evaluation was done in the energy range form 1e-5 eV to 10 keV with the SAMMY code[ref1]. Capture and transmission measurements for enriched W-184 and natural tungsten were used in the evaluation. The measurements were done at the Oak Ridge Linear Accelerator (ORELA)[ref2] and at the Geel Linear Accelerator (GELINA), Belgium[ref3]. Neutron transmission and capture data were measured in the energy range from 20 eV to 10 keV. Thermal cross section[ref4] data available in the EXFOR library were also used in the evaluation. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process in the energy region 1e-5 eV-10 keV. The RML formalist (LRF=7) was used for the resonance parameters and the compact formalism (LCOMP=2) for the covariance matrix. Thermal cross section and uncertainty calculated with SAMMY and the PUFF codes are compared with the values listed in the ATLAS of Neutron Resoances in the table below. Also shown is the capture resonance integral, Coherent scattering length and the effective radius R'. Cross Section ORNL (b) Atlas (b) ------------- -------- --------- Total 8.98 +/- 0.12 - Capt 1.63 +/- 0.13 1.70 +/- 0.10 Scat 7.35 +/- 0.10 7.35 +/- 0.10 Capture Res. Int. 16.01 +/- 0.17 14.7 +/- 1.5 R' 7.62 fm 8.0 +/- 0.2 fm b_coher 7.41 fm 7.55e +/- 0.06 fm Average cross section and related uncertainties calculated in energy group 0.0253 eV - 0.3 eV are listed in the table below. Cross Section Average Value (b) ------------- ----------------- Total 8.89 +/- 0.12 (1.3%) Capt 1.56 +/- 0.11 (7.0%) Scat 7.33 +/- 0.11 (1.5%) [ref 1] N. M. Larson,"Updated Users' Guide for SAMMY," Oak Ridge National Laboratory report ORNL/TM-9179/R6 (2003). [ref 2] K. Guber, private communication (2012). [ref 3] C. Lampoudis, K. Guber, S. Kopecky, et al., J. Korean Phys. Soc. 59, 1860 (2010). [ref 4] S. J. Friesenhahn, E. Haddad, F.H. Froehner, et al., Nucl. Sci. Eng. 26, 487 (1966). * n-074_W_186.endf: 74-W- 186 ORNL Resonance Evaluation Including Covariance (ORNL AUG 2014) L. Leal, M. Pigni, K. Guber, D. Wiarda, and G. Arbanas W-186 resolved resonance parameter evaluation was done in the energy range form 1e-5 eV to 10 keV with the SAMMY code[ref1]. Capture and transmission measurements for enriched W-186 and natural tungsten were used in the evaluation. The measurements were done at the Oak Ridge Linear Accelerator (ORELA)[ref2] and at the Geel Linear Accelerator (GELINA), Belgium[ref3]. Neutron transmission and capture data were measured in the energy range from 20 eV to 10 keV. Thermal cross section[ref4] data available in the EXFOR library were also used in the evaluation. Resonance parameter covariance matrices were also obtained in the SAMMY evaluation process in the energy region 1e-5 eV-10 keV. The RML formalist (LRF=7) was used for the resonance parameters and the compact formalism (LCOMP=2) for the covariance matrix. Thermal cross section and uncertainty calculated with SAMMY and the PUFF codes are compared with the values listed in the ATLAS of Neutron Resoances in the table below. Also shown is the capture resonance integral, Coherent scattering length and the effective radius R'. Cross Section ORNL (b) Atlas (b) ------------- -------- --------- Total 37.97 +/- 0.59 - Capt 37.88 +/- 0.59 38.1 +/- 0.5 Scat 0.09 +/- 0.02 0.07 +/- 0.01 Capture Res. Int. 476.01 +/- 7.43 480.0 +/- 15.0 R' 7.75 fm 7.64 +/- 0.05 fm b_coher -0.76 fm -0.73 +/- 0.06 fm Average cross section and related uncertainties calculated in energy group 0.0253 eV - 0.3 eV are listed in the table below. Cross Section Average Value (b) ------------- ----------------- Total 36.37 +/- 0.57 ( 1.6%) Capt 36.28 +/- 0.57 ( 1.6%) Scat 0.09 +/- 0.02 (28.2%) [ref 1] N. M. Larson,"Updated Users' Guide for SAMMY," Oak Ridge National Laboratory report ORNL/TM-9179/R6 (2003). [ref 2] K. Guber, private communication (2012). [ref 3] C. Lampoudis, K. Guber, S. Kopecky, et al., J. Korean Phys. Soc. 59, 1860 (2010). [ref 4] S. J. Friesenhahn, E. Haddad, F.H. Froehner, et al., Nucl. Sci. Eng. 26, 487 (1966). New fast region evaluations: * n-018_Ar_040.endf: New evaluation above the resonance region, which fixes the EPMAX problem reported at CSEWG in 2011. Other notable changes: * Add thermal neutron primary gammas from EGAF library (B. Sleaford, LLNL & R. Firestone, LBNL) to: n-003_Li_006.endf, n-003_Li_007.endf, n-005_B_011.endf, n-011_Na_023.endf, n-013_Al_027.endf, n-014_Si_028.endf, n-017_Cl_035.endf, n-017_Cl_037.endf * Convert MeV^-1 -> eV^-1 in energy release from fission (MT458) resolving issue #696 (Patch from C. Mattoon). Affects many minor actinides: n-089_Ac_225.endf, n-089_Ac_226.endf, n-089_Ac_227.endf, n-090_Th_228.endf, n-090_Th_230.endf, n-090_Th_231.endf, n-090_Th_233.endf, n-090_Th_234.endf, n-091_Pa_229.endf, n-091_Pa_230.endf, n-091_Pa_231.endf, n-091_Pa_232.endf, n-091_Pa_233.endf, n-092_U_230.endf, n-092_U_231.endf, n-092_U_237.endf, n-092_U_239.endf, n-092_U_241.endf, n-093_Np_234.endf, n-093_Np_235.endf, n-093_Np_236.endf, n-093_Np_239.endf, n-094_Pu_236.endf, n-094_Pu_237.endf, n-094_Pu_238.endf, n-094_Pu_243.endf, /n-094_Pu_244.endf, n-094_Pu_246.endf, n-095_Am_240.endf, n-095_Am_242.endf, n-095_Am_242m1.endf, n-096_Cm_240.endf, n-096_Cm_241.endf, n-096_Cm_247.endf, n-096_Cm_249.endf, n-096_Cm_250.endf, n-097_Bk_245.endf, n-097_Bk_246.endf, n-097_Bk_247.endf, n-097_Bk_248.endf, n-097_Bk_249.endf, n-097_Bk_250.endf, n-098_Cf_246.endf, n-098_Cf_248.endf, n-098_Cf_250.endf, n-098_Cf_252.endf, n-098_Cf_253.endf, n-098_Cf_254.endf Fixes: * n-001_H_003.endf: Fixing incorrect reference #3 (wrong journal/page numbers) (C. Mattoon) * n-006_C_000.endf: Since the MT=5 cross section is zero at and below 2e7, set the neutron multiplicity to zero as well. (B. Beck) * n-005_B_011.endf: Several fixes: ** T. Kawano recomputed the elastic angular distribution with the same optical model, but with higher Lmax. This resolves tracker #925 ** For MT=102, the number of g's in MF=14 was 5. It should have been 9 like in MF=12. * n-009_F_019.endf: Fix count of gammas in MT=102 * n-011_Na_023.endf: Update NK in MF=14 MT=102 to agree with MF=12 MT=102 * n-017_Cl_035.endf: Several fixes: ** Tweaked the (n,p) background cross section by one point to remove a discontinuity and resolve tracker item #845 (T. Kawano) ** Fix top end of MF=12 MT=102 gamma multiplicities: incorrectly entered as 2.000000+0 instead of 2.000000+7 (C. Mattoon) * n-017_Cl_037.endf: Several fixes: ** Fix top end of MF=12 MT=102 gamma multiplicities: incorrectly entered as 2.000000+0 instead of 2.000000+7 (C. Mattoon) * n-020_Ca_040.endf: Fix the gap in the transition from the RR to the high energy region. This resolves the second half of tracker item #709 (C. Mattoon) * n-027_Co_058.endf: Resolve the Co58 half of issue #709 with Caleb Mattoon's patch -- it appears that the transition between RR and high energy region was goofed up, so Caleb patched the transition. * n-028_Ni_058.endf: All cross sections above the resonance regions were upgraded (T. Kawano) * n-028_Ni_059.endf: All cross sections above the resonance regions were upgraded (T. Kawano) * n-028_Ni_060.endf: All cross sections above the resonance regions were upgraded (T. Kawano) * n-028_Ni_061.endf: All cross sections above the resonance regions were upgraded (T. Kawano) * n-028_Ni_062.endf: All cross sections above the resonance regions were upgraded (T. Kawano) * n-028_Ni_064.endf: All cross sections above the resonance regions were upgraded (T. Kawano) * n-036_Kr_078.endf: Fix background cross sections in resonance region (C. Mattoon) * n-029_Cu_065.endf: The range of the resolved range in 65-Cu was erraneously set to 1.3e6 eV instead of 3e5 eV. This update fixes this error. We also eliminated repeated zeros in file 3 for the RR range (D. Wiarda) * n-030_Zn_068.endf: MF9 weights were incorrect in that they should have extended up to the first excited state (2.1 MeV) rather than the upper end of the MF=3 domain (2.0 MeV) (C. Mattoon) * n-038_Sr_088.endf: Revised 7 resonance widths that appear to have been mistranscribed when translating from the Atlas of Neutron Resonance into END/B-VII: 26.98 keV Gn, three orders smaller than what it should be. 73.77 keV Gn, three orders smaller than what it should be. 75.5 keV Gg, three orders smaller than what it should be. 181.1 keV Gg, three orders smaller than what it should be. 214.3 keV Gn, three orders smaller than what it should be. 268 keV Gn, three orders smaller than what it should be. 297.8 keV Gg, three orders smaller than what it should be. This problem was noted by Tatsuya Katabuchi (JAEA) * n-039_Y_089.endf: Applied & checked a patch * n-040_Zr_090.endf: Several fixes: ** Revised resonance parameters (ref. S. Mughabghab, March 2012) ** Change to LSSF=1 * n-040_Zr_091.endf: Revised resonance parameters (ref. S. Mughabghab, March 2012) * n-040_Zr_092.endf: Several fixes: ** Revised resonance parameters (ref. S. Mughabghab, March 2012) ** Change to LSSF=1 * n-040_Zr_094.endf: Several fixes: ** Revised resonance parameters (ref. S. Mughabghab, March 2012) ** Change to LSSF=1 * n-040_Zr_096.endf: Several fixes: ** Revised resonance parameters (ref. S. Mughabghab, March 2012) ** Change to LSSF=1 * n-041_Nb_093.endf: applied patch from Caleb Mattoon, resolving issue #693: The MT51, MF3 level energy didn't agree with those in MFs 8. 10 and 40. We picked the level recommended by ENSDF * n-045_Rh_105.endf: Adopt 105Rh from JENDL-4.0. The JENDL-3.2 evaluation and the ENDF/B-VII.1 evaluation were identical and both a result of the WPEC/SG-23 project. The JENDL-4.0 update revised the resonance region, fixing a long standing bug with the resonance spin assignments * n-050_Sn_120.endf: Adjust the gamma branching ratios out of level 18 (MT=68) so they sum to 1, high energy part replaced by new CoH3 calculations to fix the reported energy balance problem. * n-050_Sn_122.endf: Fix typo in original formatting of resonances during translation from the Atlas to ENDF. This eliminates several warnings from PSYCHE and partly resolves ENDF tracker #220 * n-050_Sn_124.endf: Fix typo in original formatting of resonances during translation from the Atlas to ENDF * n-051_Sb_124.endf: Fixes to outgoing spectra (T. Kawano) * n-053_I_127.endf: Fix the MF8 MT107 QI, This cleared up a warning on ADVANCE. * n-054_Xe_123.endf: recalculate the (n,tot) cross section with the correct energy grid that avoids interpolations troubles (I. Thompson) * n-054_Xe_124.endf: recalculate the (n,tot) cross section with the correct energy grid that avoids interpolations troubles (I. Thompson) * n-054_Xe_124.endf: Fix background cross sections in resonance region (C. Mattoon) * n-062_Sm_151.endf: Fixes to outgoing spectra (T. Kawano) * n-062_Sm_154.endf: Fix error in evaluation documentation * n-063_Eu_153.endf: Many fixes: ** (n,g)'s gamma multiplicity table (MT102, MF6, very top of MF) had zero gamma multiplicity at Ein=10e-5 eV. ** Copied down Ein=1 keV multiplicity (4.12535) and resolved a tracker item. ** Energy spectra and angular distributions recalculated using CoH * n-069_Tm_168.endf: Fix MF=6 MT=102, first energy point was replaced by an actual distribution, which is the same of the next incident energy (30eV), but with 30eV subtracted in the last two outgoing energies (G. Nobre). * n-073_Ta_180.endf: Recalculate the (n,tot) cross section with the correct energy grid that avoids interpolations troubles (I. Thompson) * n-073_Ta_181.endf: Several fixes: ** Recalculate the (n,tot) cross section with the correct energy grid that avoids interpolations troubles (I. Thompson) ** Fixes to cross sections & distributions to get energy ranges to match (I. Thompson) * n-075_Re_185.endf: Several fixes: ** Modified R', the potential scattering radius, to match the latest fits from S. Mughabghab: R' = 8.25+/-0.19 fm, S0 = 1.93+/-0.06, and S2 = 2.08+/-0.33. S1 is too small to determine. For details, see S.F. Mughabghab, Nuclear Data Sheets, 118, 287, 2014 ** Fix background cross sections in resonance region (C. Mattoon) ** Recalculate the (n,tot) cross section with the correct energy grid that avoids interpolations troubles (I. Thompson) ** Fixes to cross sections & distributions to get energy ranges to match (I. Thompson) * n-075_Re_187.endf: Several fixes: ** Modified R', the potential scattering radius, to match the latest fits from S. Mughabghab: R' = 8.25+/-0.19 fm, S0 = 1.93+/-0.06, and S2 = 2.08+/-0.33. S1 is too small to determine. For details, see S.F. Mughabghab, Nuclear Data Sheets, 118, 287, 2014 ** Fix background cross sections in resonance region (C. Mattoon) ** Recalculate the (n,tot) cross section with the correct energy grid that avoids interpolations troubles (I. Thompson) * n-082_Pb_208.endf: Fix QM & QI for several levels in the 600-range * n-090_Th_232.endf: Several fixes: ** Resonance enenrgy 8.358395 eV in MF32 corrected to 8.358396 eV (A. Trkov) ** Densified energy grid at low energy tail of the fission spectra (A. Trkov) * n-095_Am_242m1.endf: Fix level index (LIS) for the target. The metastable level in Am244 is the 2nd excited level, not the first * LFS indicates final level index (not metastable number) in the residual. Several files had LFS=1 for metastables that are actually higher states: (n-025_Mn_055.endf, n-040_Zr_090.endf, n-040_Zr_091.endf, n-069_Tm_168.endf, n-069_Tm_169.endf, n-069_Tm_170.endf). This fixes NNDCforge tracker item #823 * Bug fixes in many evaluations (n-000_n_001.endf, n-003_Li_006.endf, n-003_Li_007.endf, n-005_B_011.endf, n-009_F_019.endf, n-008_O_018.endf) * Fixed NLIB designator in many many files.