IRDF2002 in metrology format cross sections (050112) 6000 0 0 3.00600E+3 5.96340E+0 0 0 34 10 325 1451 0.0 0.0 0 0 0 6 325 1451 1.00000E+0 2.00000E+7 0 0 10 2002 325 1451 3.00000E+2 0.0 1 0 237 3 325 1451 3-Li- 6 LANL EVAL-APR89 G.M.HALE, P.G.YOUNG 325 1451 DIST-Feb2004 325 1451 ----IRDF-2002 MATERIAL 325 325 1451 -----INCIDENT NEUTRON DATA 325 1451 ------ENDF-6 FORMAT 325 1451 ****************************************************************** 325 1451 3-LI - 6 LANL EVAL-APR89 G.M.HALE, P.G.YOUNG 325 1451 DIST-SEP91 REV1-JUL91 19910806 325 1451 ----ENDF/B-VI MATERIAL 325 REVISION 1 325 1451 ****************************************************************** 325 1451 3-LI - 6 LANL EVAL-APR89 G.M.HALE, P.G.YOUNG 325 1451 DIST-FEB91 910201 325 1451 ----ENDF/B-VI MATERIAL 325 325 1451 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 325 1451 DOSIMETRY 325 1451 ****************************************************************** 325 1451 891221 325 1451 ----ENDF/B-VI MATERIAL 325 325 1451 325 1451 ****************************************************************** 325 1451 325 1451 ***************************************************************** 325 1451 ***************************************************************** 325 1451 325 1451 MOD1 OF ENDF/B-VI 325 1451 325 1451 The following revisions were made for MOD1 of ENDF/B-VI: 325 1451 325 1451 1. MF=1,MT=451 - Comments were added regarding estimated 325 1451 (expanded) covariance for the Standards Cross Sections. 325 1451 2. MF=3,MT=53 - LF flag and Q-value corrected. 325 1451 325 1451 ***************************************************************** 325 1451 ****************************************************************** 325 1451 325 1451 ENDF/VI EVALUATION 325 1451 G. M. Hale and P. G. Young 325 1451 325 1451 MAJOR CHANGES FROM VERSION V OF ENDF/B ARE: 325 1451 325 1451 1. Inclusion of the ENDF/B-VI standard (n,t) cross section 325 1451 from the simultaneous standards analysis (ca85) over the 325 1451 energy range thermal to 1 MeV. 325 1451 2. Replacement of all major cross sections and elastic angular 325 1451 distributions at energies between 10^-5 eV and 3 MeV with 325 1451 results from the R-matrix analysis performed in conjunction 325 1451 with the simultaneous standards analysis. 325 1451 3. Revision of the elastic cross sections and angular distri- 325 1451 butions at energies between 3 and 20 MeV to match recent 325 1451 experimental data, resulting in a general decrease of the 325 1451 elastic cross section in this energy range. 325 1451 4. Revision of the (n,n')d cross sections to account for 325 1451 recent measurements, resulting in a general increase in 325 1451 the total (n,n')d cross section that tends to offset the 325 1451 decrease in the elastic cross section and maintain about 325 1451 the same total cross section as before. 325 1451 325 1451 325 1451 ****************************************************************** 325 1451 325 1451 STANDARDS COVARIANCES 325 1451 325 1451 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 325 1451 expressed the concern that the uncertainties resulting from the 325 1451 combination of R-matrix and simultaneous evaluations might have 325 1451 led to uncertainties that are too small. As a result, the 325 1451 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 325 1451 a set of expanded covariance estimates for the standard cross 325 1451 section reactions. These uncertainties are estimates such that 325 1451 if a modern day experiment were performed on a given standard 325 1451 cross section using the best techniques, approximately 2/3 of 325 1451 the results should fall within these expanded uncertainties. The 325 1451 expanded uncertainties for the Li-6(n,t) cross section are given 325 1451 in the following table and are compared to values from the 325 1451 combined output of the standards covariance analysis: 325 1451 325 1451 Energy Range Estimated Uncertainty Combined Analysis 325 1451 (keV) (percent) (percent) 325 1451 325 1451 1.0E-08 - 0.1 0.3 0.14 325 1451 0.1 - 1.0 0.5 325 1451 1.0 - 10. 0.7 0.14 325 1451 10. - 50. 0.9 325 1451 50. - 90. 1.1 0.25 325 1451 90. - 150 1.5 325 1451 150 - 450 2.0 0.29 325 1451 450 - 650 5.0 325 1451 650 - 800 2.0 0.36 325 1451 800 - 1000 5.0 325 1451 325 1451 **************************************************************** 325 1451 325 1451 325 1451 mf=2 --------- resonance parameters ---------------------------- 325 1451 325 1451 mt=151 effective scattering radius = 2.31175e-13 cm. 325 1451 325 1451 mf=3 --------- smooth cross sections --------------------------- 325 1451 325 1451 the 2200 m/s cross sections are as follows: 325 1451 mt=1 sigma = 941.6928 barns 325 1451 mt=2 sigma = 0.67157 barns 325 1451 mt=102 sigma = 0.03850 barns 325 1451 mt=105 sigma = 940.9827 barns 325 1451 325 1451 mt=105 (n,t) cross section 325 1451 below 3 mev, values are taken from the r-matrix analysis, 325 1451 which includes (n,t) measurements from re78, la78, br77, 325 1451 ov74, and ba75. between 3 and 5 mev, the values are 325 1451 based on ba75, and at higher energies are taken from the 325 1451 evaluation of pe64, extended to 20 mev considering the 325 1451 data of ke58. 325 1451 325 1451 325 1451 325 1451 mf=33----------cross section covariances------------------------- 325 1451 (to be added later) 325 1451 325 1451 the relative covariances for mt=1,2, and 105 below 4 mev are 325 1451 given in file 33. they are based on calculations using the co- 325 1451 variances of the r-matrix parameters in first-order error 325 1451 propogation. 325 1451 mt=1 total 325 1451 relative covariances entered as nc-type sub-subsection, 325 1451 implying that they are to be constructed from those for 325 1451 mt=2 and 105. they are not intended for use at energies 325 1451 above 4 mev. 325 1451 mt=2,105 elastic and (n,t) 325 1451 relative covariances among these two cross sections are 325 1451 entered explicitly as ni-type sub-subsections in the 325 1451 lb=5 (direct) representation at energies below 4 mev. 325 1451 although values for the 3.95-4.05 mev bin are repeated 325 1451 in a 4-20 mev bin, the covariances are not intended for 325 1451 use at energies above 4 mev. 325 1451 325 1451 325 1451 --------------------- references -------------------------------- 325 1451 325 1451 ab70 U.Abbondanno, Nuo.Cim. A166,139(1970). 325 1451 aj74 f.ajzenberg-selove and t.lauritsen, nucl. phys. a227,55 325 1451 (1974). 325 1451 ar64 a.h.armstrong, j.gammel, l.rosen, and g.m.frye, nucl. phys. 325 1451 52,505 (1964). 325 1451 as63 v.j.ashby et al, phys. rev. 129,1771 (1963). 325 1451 ba53 m.e.battat and f.l.ribe, phys.rev. 89,80 (1953). 325 1451 ba63 r.batchelor and j.h.towle, nucl. phys. 47,385 (1963). 325 1451 ba65 r.bass, c.bindhardt, and k.kruger, eandc(e)-57u (1965). 325 1451 ba75 c.m.bartle, proc. conf. on nuclear cross sections and 325 1451 technology, vol.2,688 (1975), and private communication 325 1451 (1976). see also nucl. phys. a330, 1 (1979). 325 1451 be75 besotosnyj et al., yk-19, 77 (1975). 325 1451 br77 r.e.brown,g.g.ohlsen,r.f.haglund, and n.jarmie, phys. rev. 325 1451 16c, 513 (1977). 325 1451 ca85 a.d.carlson,w.p.poenitz,g.m.hale, and r.w.peele, nuclear 325 1451 data for basic and applied science (santa fe, n.m.), 1429 325 1451 (1985). 325 1451 co67 j.a.cookson and d.dandy, nucl. phys. a91,273 (1967). 325 1451 co82 h.conde,t.andersson,l.nilsson, and c.nordborg, nuclear data 325 1451 for science and technology (antwerp, belgium), 447 (1982). 325 1451 de73 F.Demanins et al., infn/be-73 (1973). 325 1451 dr82 m.drosg,d.m.drake,r.a.hardekopf, and g.m.hale, la-9129-ms 325 1451 (1982). 325 1451 dr85 m.drosg et al., santa fe conf.1, 145(1985). 325 1451 fo71 d.g.foster and d.w.glasgow, phys. rev. c3,576 (1971). 325 1451 fr54 g.m.frye, phys. rev. 93,1086 (1954). 325 1451 go72 c.a.goulding and p.stoler, eandc(us)-176u,161 (1972). 325 1451 ha75 j.a.harvey and n.w.hill, nuclear cross sections and 325 1451 technology (washington, d.c.), 244 (1975). 325 1451 ha84 g.m.hale, nuclear standard reference data (geel,belgium) 325 1451 iaea tecdoc-335, 103 (1984). describes preliminary analysis. 325 1451 ho68 j.c.hopkins,d.m.drake, and h.conde, nucl. phys. a107,139 325 1451 (1968), and j.c.hopkins, d.m.drake, and h.conde, la-3765 325 1451 (1967). 325 1451 ho79 h.h.hogue et al., n.s.&e. 69, 22 (1979). 325 1451 ju73 e.t.jurney, lasl, private communication (1973). 325 1451 ke58 r.d.kern and w.e.kreger, phys. rev. 112, 926 (1958). 325 1451 ke79 j.d.kellie,g.p.lamaze, and r.b.schwartz, nuclear cross 325 1451 sections for technology (knoxville, tn.), 48 (1979). 325 1451 kn77 h.h.knitter,c.budtz-jorgensen,m.mailly, and r.vogt, eur- 325 1451 5726e (1977). 325 1451 kn79 h.d.knox,r.m.white, and r.o.lane, n.s.&e. 69, 223 (1979). 325 1451 kn83 h.h.knitter,c.budtz-jorgensen,d.l.smith, and d.marletta, 325 1451 n.s.&e. 83, 229(1983). 325 1451 la61 r.o.lane,a.s.langsdorf,j.e.monahan, and a.j.elwyn, ann. 325 1451 phys.12, 135 (1961). 325 1451 la78 g.p.lamaze,o.a.wasson,r.a.schrack, and a.d.carlson, n.s.&e. 325 1451 68, (1978). 325 1451 li80 p.w.lisowski et al., la-8342 (1980). 325 1451 ma69 d.s.mather and l.f.paine, awre-o-47/69 (1969). 325 1451 me65 f.merchez,n.v.sen,v.regis, and r.bouchez, compt. rend. 260, 325 1451 3922 (1965). 325 1451 ov74 j.c.overley,r.m.sealock, and d.h.ehlers, nucl. phys. a221, 325 1451 573 (1974). 325 1451 pe64 e.d.pendlebury, awre-o-60/64 (1964). 325 1451 pr69 g.presser et al., nuc.phys. a131, 679(1969). 325 1451 re78 c.renner,j.a.harvey,n.w.hill,g.l.morgan, and k.pusk, bull. 325 1451 am. phys. soc. 23, 526 (1978). 325 1451 sa82 e.t.sadowski,h.knox,d.a.resler, and r.o.lane, bap 27,624(c5) 325 1451 (1982). 325 1451 sm77 a.b.smith,p.guenther,d.havel, and j.f.whalen, anl/ndm-29 325 1451 (1977). 325 1451 sm82 a.b.smith,p.t.guenther, and j.f.whalen, nucl. phys. a373, 325 1451 305 (1982). 325 1451 wo62 c.wong,j.d.anderson, and j.w.mcclure, nucl. phys. 33,680 325 1451 (1962). 325 1451 ****************************************************************** 325 1451 325 1451 325 1451 325 1451 325 1451 ****************************************************************** 325 1451 325 1451 ***************** Program LINEAR (VERSION 2002-1) *************** 325 1451 For All Data Greater than 1.0000E-10 barns in Absolute Value 325 1451 Data Linearized to Within an Accuracy of .100000000 per-cent 325 1451 ***************** Program SIGMA1 (VERSION 2002-1) *************** 325 1451 Data Doppler Broadened to 300.000000 Kelvin 325 1451 for All Data Greater than 1.0000E-10 barns in Absolute Value 325 1451 Data Linearized to Within an Accuracy pf .100000000 per-cent 325 1451 ***************** Program FIXUP (Version 2002-1) **************** 325 1451 Corrected ZA/AWR in All Sections-----------------------------Yes 325 1451 Corrected Thresholds-----------------------------------------Yes 325 1451 Extended Cross Sections to 20 MeV----------------------------No 325 1451 Allow Cross Section Deletion---------------------------------No 325 1451 Allow Cross Section Reconstruction---------------------------No 325 1451 Make All Cross Sections Non-Negative-------------------------Yes 325 1451 Delete Energies Not in Ascending Order-----------------------Yes 325 1451 Deleted Duplicate Points-------------------------------------Yes 325 1451 Check for Ascending MAT/MF/MT Order--------------------------Yes 325 1451 Check for Legal MF/MT Numbers--------------------------------Yes 325 1451 Allow Creation of Missing Sections---------------------------No 325 1451 Allow Insertion of Energy Points-----------------------------No 325 1451 Create Uniform Energy Grid-----------------------------------No 325 1451 Delete Section if Cross Section =0 at All Energies-----------Yes 325 1451 ***************** Program GROUPIE (VERSION 2002-1) ************** 325 1451 Unshielded Group Averages Using 640 Groups 325 1451 Weighting Spectrum: Flat (Constant) Spectrum 325 1451 1 451 244 2 325 1451 3 105 217 1 325 1451 33 105 33 1 325 1451 325 1 0 325 0 0 3.00600E+3 5.96340E+0 0 0 0 0 325 3105 4.78380E+6 4.78380E+6 0 0 1 641 325 3105 641 1 325 3105 .000100000 14794.9461 .000105000 14449.9534 .000110000 14122.2061 325 3105 .000115000 13820.1942 .000120000 13467.1458 .000127500 13075.4530 325 3105 .000135000 12717.5721 .000142500 12388.6847 .000150000 12032.7367 325 3105 .000160000 11661.9312 .000170000 11324.5439 .000180000 11014.8459 325 3105 .000190000 10726.6978 .000200000 10463.6234 .000210000 10216.1135 325 3105 .000220000 9986.21324 .000230000 9772.62292 .000240000 9521.91859 325 3105 .000255000 9246.40272 .000270000 9033.79728 .000280000 8797.12696 325 3105 .000300000 8508.50325 .000320000 8247.16668 .000340000 8007.82467 325 3105 .000360000 7787.37574 .000380000 7586.13528 .000400000 7376.33068 325 3105 .000425000 7161.64277 .000450000 6965.50583 .000475000 6785.66231 325 3105 .000500000 6616.52235 .000525000 6461.94757 .000550000 6315.93048 325 3105 .000575000 6180.13284 .000600000 6040.94642 .000630000 5897.75751 325 3105 .000660000 5766.73697 .000690000 5641.05202 .000720000 5507.32050 325 3105 .000760000 5363.93249 .000800000 5230.80234 .000840000 5108.78635 325 3105 .000880000 4992.81623 .000920000 4886.50890 .000960000 4784.70637 325 3105 .001000000 4679.19964 .001050000 4569.04414 .001100000 4465.76191 325 3105 .001150000 4370.59678 .001200000 4258.33842 .001275000 4134.96155 325 3105 .001350000 4022.16216 .001425000 3916.88925 .001500000 3805.04153 325 3105 .001600000 3688.10030 .001700000 3581.34573 .001800000 3482.60854 325 3105 .001900000 3392.40441 .002000000 3308.77765 .002100000 3230.31157 325 3105 .002200000 3158.44480 .002300000 3089.72099 .002400000 3011.30697 325 3105 .002550000 2924.17510 .002700000 2856.02126 .002800000 2781.96182 325 3105 .003000000 2690.80549 .003200000 2607.85391 .003400000 2531.98785 325 3105 .003600000 2462.79638 .003800000 2398.91608 .004000000 2332.33692 325 3105 .004250000 2264.72689 .004500000 2203.02081 .004750000 2145.35559 325 3105 .005000000 2092.44576 .005250000 2043.40654 .005500000 1997.05482 325 3105 .005750000 1954.57647 .006000000 1909.96714 .006300000 1865.38391 325 3105 .006600000 1823.18871 .006900000 1784.04467 .007200000 1741.48065 325 3105 .007600000 1695.96373 .008000000 1654.34447 .008400000 1615.27928 325 3105 .008800000 1578.91854 .009200000 1545.13798 .009600000 1513.00017 325 3105 .010000000 1479.73644 .010500000 1444.57603 .011000000 1412.42313 325 3105 .011500000 1381.75051 .012000000 1346.59615 .012750000 1307.68584 325 3105 .013500000 1271.64181 .014250000 1238.56317 .015000000 1203.27730 325 3105 .016000001 1166.23862 .017000001 1132.28052 .017999999 1101.28202 325 3105 .018999999 1072.79317 .020000000 1046.06875 .021000000 1021.61496 325 3105 .022000000 998.572690 .023000000 977.099923 .024000000 951.867476 325 3105 .025500000 924.650334 .027000001 903.085714 .028000001 879.664218 325 3105 .029999999 850.841313 .032000002 824.584971 .034000002 800.612528 325 3105 .035999998 778.732778 .037999999 758.549586 .039999999 737.487875 325 3105 .042500000 716.110259 .045000002 696.571444 .047499999 678.366928 325 3105 .050000001 661.623345 .052499998 646.130877 .055000000 631.464013 325 3105 .057500001 618.035173 .059999999 603.916290 .063000001 589.802419 325 3105 .066000000 576.497152 .068999998 564.095301 .071999997 550.648650 325 3105 .075999998 536.246480 .079999998 523.089245 .083999999 510.719324 325 3105 .088000000 499.211911 .092000000 488.553833 .096000001 478.374129 325 3105 .100000001 467.864268 .104999997 456.740352 .109999999 446.578283 325 3105 .115000002 436.871661 .119999997 425.753899 .127499998 413.473559 325 3105 .135000005 402.085828 .142499998 391.626836 .150000006 380.471804 325 3105 .159999996 368.744950 .170000002 358.015375 .180000007 348.198886 325 3105 .189999998 339.184378 .200000003 330.720268 .209999993 322.982244 325 3105 .219999999 315.682189 .230000004 308.885854 .239999995 301.048031 325 3105 .254999995 292.298232 .270000011 285.625887 .280000001 278.184188 325 3105 .300000012 269.039086 .319999993 260.740769 .340000004 253.189079 325 3105 .360000014 246.269336 .379999995 239.820982 .400000006 233.210767 325 3105 .425000012 226.472440 .449999988 220.243253 .474999994 214.511408 325 3105 .500000000 209.256293 .524999976 204.282890 .550000012 199.729453 325 3105 .574999988 195.403926 .600000024 190.991063 .629999995 186.517846 325 3105 .660000026 182.279486 .689999998 178.400407 .720000029 174.092531 325 3105 .759999990 169.580921 .800000012 165.402550 .839999974 161.482057 325 3105 .879999995 157.896838 .920000017 154.457639 .959999979 151.313264 325 3105 1.00000000 147.924471 1.04999995 144.457738 1.10000002 141.215388 325 3105 1.14999998 138.163257 1.20000005 134.661002 1.27499998 130.732247 325 3105 1.35000002 127.134297 1.42499995 123.849352 1.50000000 120.293925 325 3105 1.60000002 116.585459 1.70000005 113.209752 1.79999995 110.125223 325 3105 1.89999998 107.244386 2.00000000 104.595170 2.09999990 102.145940 325 3105 2.20000005 99.8337043 2.29999995 97.7171215 2.40000010 95.2040034 325 3105 2.54999995 92.4334553 2.70000005 90.3148276 2.79999995 87.9381155 325 3105 3.00000000 85.0523601 3.20000005 82.4380221 3.40000010 80.0560785 325 3105 3.59999990 77.8616733 3.79999995 75.8730582 4.00000000 73.7205775 325 3105 4.25000000 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32533105 7.915241-7 9.299034-6 8.280879-6 5.098584-6 1.338568-6 1.841448-6 32533105 1.270541-5 1.262244-5 7.390554-6 4.714562-6 1.835564-5 1.767288-5 32533105 9.582569-6 3.027060-5 1.780456-5 3.434466-5 32533105 32533 0 325 0 0 0 0 0 5.00000E+3 1.07191E+1 -1 0 34 0 500 1451 0.0 0.0 0 0 0 6 500 1451 1.00000E+0 2.00000E+7 0 0 10 2002 500 1451 3.00000E+2 0.0 1 0 75 2 500 1451 5-B - 0 NDS IAEA-JAN04 500 1451 DIST-Feb2004 500 1451 ----IRDF-2002 500 1451 -----INCIDENT NEUTRON DATA 500 1451 ------ENDF-6 FORMAT 500 1451 ***************************************************************** 500 1451 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 500 1451 DOSIMETRY Assembled at NDS from the ENDF/B-VI evaluations for 500 1451 5-B -10 and 5-B -11. The files were processed 500 1451 through the 2002 pre-processing codes LINEAR,RECENT, 500 1451 SIGMA1 and FIXUP to produce pointwise files prior to 500 1451 input to MIXER. 500 1451 500 1451 MIXER INPUT FILE 500 1451 500 1451 Boron DENSITY 2.34 G/CC. CONSTITUENTS: 10-19.8 11-80.2 500 1451 FIXUP.out 500 1451 MIXER.OUT 500 1451 5000 500 3 1 (ID FOR COMBINED REACTION) 500 1451 5010 1 0.429086 500 1451 5011 1 1.910914 500 1451 (BLANK LINE TERMINATES LIST) 500 1451 ****************************************************************** 500 1451 500 1451 5-B - 10 LANL EVAL-NOV89 G.M.HALE, P.G.YOUNG 500 1451 DIST-SEP91 REV1-JUL91 19910806 500 1451 ----ENDF/B-VI MATERIAL 525 REVISION 1 500 1451 ***************************************************************** 500 1451 5-B - 11 LANL EVAL-MAY89 P.G.YOUNG 500 1451 DIST-SEP 1 REV1- 20010926 500 1451 ----ENDF/B-VI MATERIAL 528 500 1451 ***************** Program MIXER (VERSION 2002-1) **************** 500 1451 Boron DENSITY 2.34 G/CC. CONSTITUENTS: 10-19.8 500 1451 11-80.2 500 1451 ---------------------------------------- 500 1451 Composition 500 1451 ---------------------------------------- 500 1451 Isotope MF MT Atom-Fract Grams/cc 500 1451 ---------------------------------------- 500 1451 5010 3 1 .198003533 .429086000 500 1451 5011 3 1 .801996467 1.91091400 500 1451 ---------------------------------------- 500 1451 5000 3 1 1.00000000 2.34000000 500 1451 ---------------------------------------- 500 1451 Composition 500 1451 ---------------------------------------- 500 1451 Isotope MF MT Atom-Fract Grams/cc 500 1451 ---------------------------------------- 500 1451 5010 3 101 .198003533 .429086000 500 1451 5011 3 101 .801996467 1.91091400 500 1451 ---------------------------------------- 500 1451 5000 3 101 1.00000000 2.34000000 500 1451 ---------------------------------------- 500 1451 Composition 500 1451 ---------------------------------------- 500 1451 Isotope MF MT Atom-Fract Grams/cc 500 1451 ---------------------------------------- 500 1451 5010 3 102 .198003533 .429086000 500 1451 5011 3 102 .801996467 1.91091400 500 1451 ---------------------------------------- 500 1451 5000 3 102 1.00000000 2.34000000 500 1451 ---------------------------------------- 500 1451 Composition 500 1451 ---------------------------------------- 500 1451 Isotope MF MT Atom-Fract Grams/cc 500 1451 ---------------------------------------- 500 1451 5010 3 107 .198003533 .429086000 500 1451 5011 3 107 .801996467 1.91091400 500 1451 ---------------------------------------- 500 1451 5000 3 107 1.00000000 2.34000000 500 1451 ---------------------------------------- 500 1451 ***************************************************************** 500 1451 ***************** Program GROUPIE (VERSION 2002-1) ************** 500 1451 Unshielded Group Averages Using 640 Groups 500 1451 Weighting Spectrum: Flat (Constant) Spectrum 500 1451 1 451 81 0 500 1451 3 1 217 0 500 1451 500 1 0 500 0 0 5.00000E+3 1.07191E+1 0 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1 12400000.0 1.42114992 12500000.0 1.42179096 12600000.0 1.42196161 500 3 1 12700000.0 1.42229522 12800000.0 1.42235987 12900000.0 1.42263263 500 3 1 13000000.0 1.42405226 13100000.0 1.42427635 13200000.0 1.42446247 500 3 1 13300000.0 1.42459770 13400000.0 1.42479286 13500000.0 1.42496373 500 3 1 13600000.0 1.42513722 13700000.0 1.42529220 13800000.0 1.42573183 500 3 1 13900000.0 1.42636889 14000000.0 1.42653165 14100000.0 1.42620005 500 3 1 14200000.0 1.42604859 14300000.0 1.42607695 14400000.0 1.42620803 500 3 1 14500000.0 1.42645059 14600000.0 1.42640948 14700000.0 1.42608295 500 3 1 14800000.0 1.42604421 14900000.0 1.42627763 15000000.0 1.42640597 500 3 1 15100000.0 1.42642142 15200000.0 1.42620980 15300000.0 1.42577383 500 3 1 15400000.0 1.42552047 15500000.0 1.42545867 15600000.0 1.42546625 500 3 1 15700000.0 1.42552674 15800000.0 1.42540050 15900000.0 1.42507008 500 3 1 16000000.0 1.42454069 16100000.0 1.42380209 16200000.0 1.42319399 500 3 1 16300000.0 1.42273229 16400000.0 1.42230819 16500000.0 1.42192518 500 3 1 16600000.0 1.42134787 16700000.0 1.42055453 16800000.0 1.41979771 500 3 1 16900000.0 1.41908886 17000000.0 1.41825331 17100000.0 1.41730518 500 3 1 17200000.0 1.41640109 17300000.0 1.41553330 17400000.0 1.41458477 500 3 1 17500000.0 1.41355380 17600000.0 1.41256255 17700000.0 1.41161949 500 3 1 17800000.0 1.41074469 17900000.0 1.40994157 18000000.0 1.40904997 500 3 1 18100000.0 1.40808103 18200000.0 1.40715562 18300000.0 1.40626368 500 3 1 18400000.0 1.40541552 18500000.0 1.40460736 18600000.0 1.40372433 500 3 1 18700000.0 1.40276326 18800000.0 1.40182117 18900000.0 1.40089943 500 3 1 19000000.0 1.39988249 19100000.0 1.39876550 19200000.0 1.39769893 500 3 1 19300000.0 1.39669575 19400000.0 1.39567395 19500000.0 1.39465125 500 3 1 19600000.0 1.39354180 19700000.0 1.39233869 19800000.0 1.39113602 500 3 1 19900000.0 1.38993562 20000000.0 0.0 500 3 1 500 3 0 500 0 0 0 0 0 5.01000E+3 9.92692E+0 0 0 34 10 525 1451 0.0 0.0 0 0 0 6 525 1451 1.00000E+0 2.00000E+7 0 0 10 2002 525 1451 3.00000E+2 0.0 1 0 256 3 525 1451 5-B - 10 LANL EVAL-NOV89 G.M.HALE, P.G.YOUNG 525 1451 DIST-Feb2004 525 1451 ----IRDF-2002 MATERIAL 525 525 1451 -----INCIDENT NEUTRON DATA 525 1451 ------ENDF-6 FORMAT 525 1451 ****************************************************************** 525 1451 5-B - 10 LANL EVAL-NOV89 G.M.HALE, P.G.YOUNG 525 1451 DIST-SEP91 REV1-JUL91 19910806 525 1451 ----ENDF/B-VI MATERIAL 525 REVISION 1 525 1451 ****************************************************************** 525 1451 5-B - 10 LANL EVAL-NOV89 G.M.HALE, P.G.YOUNG 525 1451 DIST-FEB91 910201 525 1451 ----IRDF-90 MATERIAL 525 525 1451 525 1451 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 525 1451 DOSIMETRY 525 1451 ****************************************************************** 525 1451 525 1451 MOD1 OF ENDF/B-VI 525 1451 525 1451 The following revisions were made for MOD1 of ENDF/B-VI: 525 1451 525 1451 1. MF=1,MT=451 - Comments were added regarding estimated 525 1451 (expanded) covariance for the Standards Cross Sections. 525 1451 2. MF=3,MT=55,57,62,64,65,68,70,71,73,74,76-81,83,84 - LR flags 525 1451 and Q-values corrected. 525 1451 525 1451 ***************************************************************** 525 1451 ****************************************************************** 525 1451 525 1451 ENDF/VI EVALUATION 525 1451 G. M. Hale and P. G. Young 525 1451 525 1451 MAJOR CHANGES FROM VERSION V OF ENDF/B ARE: 525 1451 525 1451 1. Inclusion of the ENDF/B-VI standard (n,alpha) and (n,alpha1) 525 1451 results from the simultaneous standards analysis (Ca85) over 525 1451 the standard energy range thermal to 100 keV. 525 1451 2. Replacement of all major cross sections and elastic angular 525 1451 distributions from 10-5 eV to 1 MeV with results from the 525 1451 R-matrix analysis performed in conjunction with the 525 1451 simultaneous standards analysis. 525 1451 3. Replaced the total cross section 1-20 MeV with results 525 1451 from a covariance analysis of available data. 525 1451 4. Revised elastic and inelastic cross sections for low-lying 525 1451 levels incorporating new elastic, inelastic, and (n,xgamma) 525 1451 experimental data. We attempted to better reconcile the 525 1451 inelastic and gamma ray data. 525 1451 5. Refit all elastic angular distributions from 1-20 MeV with 525 1451 Legendre expansions and incorporated results from new 525 1451 measurements. 525 1451 6. Fit inelastic neutron angular distributions for first 5 525 1451 excited states of B10 with Legendre expansions. 525 1451 7. Incorporated new (n,t2alpha) cross section data into MT113 525 1451 and adjusted (n,alpha) cross sections above standard region 525 1451 for better consistency with data as well as other cross 525 1451 sections (esp. total and elastic) determined by data. 525 1451 525 1451 *****Note that covariance data will be added at a later date. 525 1451 525 1451 ****************************************************************** 525 1451 525 1451 STANDARDS COVARIANCES 525 1451 525 1451 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 525 1451 expressed the concern that the uncertainties resulting from the 525 1451 combination of R-matrix and simultaneous evaluations might have 525 1451 led to uncertainties that are too small. As a result, the 525 1451 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 525 1451 a set of expanded covariance estimates for the standard cross 525 1451 section reactions. These uncertainties are estimates such that 525 1451 if a modern day experiment were performed on a given standard 525 1451 cross section using the best techniques, approximately 2/3 of 525 1451 the results should fall within these expanded uncertainties. The 525 1451 expanded uncertainties for the B-10(n,alpha0) and B-10(n,alpha1) 525 1451 cross sections are given in the following tables and are 525 1451 compared to values from the combined output of the standards 525 1451 covariance analysis: 525 1451 525 1451 525 1451 B-10(n,alpha0) Cross Section 525 1451 525 1451 Energy Range Estimated Uncertainty Combined Analysis 525 1451 (keV) (percent) (percent) 525 1451 525 1451 1.0E-08 - 0.1 0.5 0.21 525 1451 0.1 - 5.0 1.5 525 1451 5.0 - 30. 3.0 0.38 525 1451 30. - 90. 5.0 525 1451 90. - 150 10.0 0.86 525 1451 150 - 200 12.0 525 1451 200 - 250 15.0 0.79 525 1451 525 1451 525 1451 525 1451 B-10(n,alpha1) Cross Section 525 1451 525 1451 Energy Range Estimated Uncertainty Combined Analysis 525 1451 (keV) (percent) (percent) 525 1451 525 1451 1.0E-08 - 0.1 0.2 0.16 525 1451 0.1 - 5.0 0.4 525 1451 5.0 - 30. 0.6 0.20 525 1451 30. - 90. 1.0 525 1451 90. - 150 1.5 0.48 525 1451 150 - 200 2.0 525 1451 200 - 250 2.5 0.62 525 1451 525 1451 **************************************************************** 525 1451 525 1451 mf=2 --------- resonance parameters ---------------------------- 525 1451 525 1451 mt=151 effective scattering radius = 4.129038-13 cm 525 1451 525 1451 mf=3 --------- smooth cross sections --------------------------- 525 1451 525 1451 the 2200 m/s cross sections are as follows, 525 1451 mt=1 sigma = 3842.146 barns 525 1451 mt=2 sigma = 2.142435 barns 525 1451 mt=102 sigma = 0.5 barns 525 1451 mt=103 sigma = 0.000566 barns 525 1451 mt=107 sigma = 3839.496 barns 525 1451 mt=113 sigma = 0.0069993 barns 525 1451 mt=600 sigma = 0.000566 barns 525 1451 mt=800 sigma = 241.2677 barns 525 1451 mt=801 sigma = 3598.228 barns 525 1451 525 1451 mt=1 total cross section 525 1451 0 to 1 mev, calculated from r-matrix parameters obtained 525 1451 from simultaneous standards analysis (ca85) used to 525 1451 obtain the endf/b-vi standard cross sections. 525 1451 1 to 20 mev, covariance analysis of measurements of di67, 525 1451 ts62,fo61,co52,au79, and co54, constrained to match 525 1451 r-matrix fit at 1 mev. glucs covariance analysis code 525 1451 (he80) was used in the calculations. 525 1451 525 1451 525 1451 mt=107 (n,alpha) cross section 525 1451 0 to 20 mev, sum of mt=800,801. 525 1451 525 1451 mt=800 (n,alpha0) cross section 525 1451 0 to 1 mev, calculated from the r-matrix parameters 525 1451 described for mt=1. experimental (n,alpha0) data input 525 1451 to the fit were those of ma68 and da61. in addition, the 525 1451 angular distributions of va72 for the inverse reaction 525 1451 were included in the analysis. 525 1451 1 to 20 mev, based on da61 measurements, with smooth extra- 525 1451 polation from 8 to 20 mev using 14-MeV data of an69. The 525 1451 da61 data above approximately 2 mev were renormalized 525 1451 by a factor of approximately 1.4. Note that some of the 525 1451 structure seen in da61 was expanded to give consistent 525 1451 nonelastic, elastic, and total cross sections when 525 1451 compared with experimental data. 525 1451 525 1451 mt=801 (n,alpha1) cross section 525 1451 0 to 1 mev, calculated from the r-matrix parameters 525 1451 described for mt=1. experimental (n,alpha1) data in- 525 1451 cluded in the fit are those of sc76. in addition, the 525 1451 absolute differential cross-section measurements of 525 1451 se76 were included in the analysis. 525 1451 1 to 20 mev, smooth curve through measurements of da61 and 525 1451 ne70, with smooth extrapolation from 15 to 20 mev. the 525 1451 da61 data above approximately 2 mev were renormalized 525 1451 by a factor of approximately 1.4. Note that some of the 525 1451 structure seen in da61 was expanded to give consistent 525 1451 nonelastic, elastic, and total cross sections when 525 1451 compared with experimental data. 525 1451 525 1451 525 1451 525 1451 ----------------------- references ----------------------------- 525 1451 525 1451 aj75 f. ajzenberg-selove, nucl. phys. a248,6 (1975) 525 1451 aj88 f. ajzenberg-selove, nucl. phys. a490,1 (1988) 525 1451 an69 B. Antolkovic, Nuc.Phys.A139, 10 (1969). 525 1451 as70 a. asami and m.c. moxon, j.nucl.energy 24,85 (1970) 525 1451 au79 g.auchampaugh et al., nucl.sci.eng.69,30(1979) 525 1451 ba60 r.bardes and g.e. owen, phys.rev.120,1369 (1960) 525 1451 be56 r.l. becker and h.h. barschall, phys.rev.102,1384 (1956) 525 1451 bo51 c.k.bockelman et al., phys.rev. 84,69 (1951) 525 1451 bo69 d.bogart and l.l.nichols, nucl.phys.a125,463 (1969) 525 1451 ca85 a.carlson et al., nuc.data for basic & applied science, 525 1451 santa fe, nm (1985) p.1429. 525 1451 co52 j.h.coon et al., phys.rev. 88,562 (1952) 525 1451 co54 c.f.cook and t.w. bonner,phys.rev. 94,651 (1954) 525 1451 co67 s.a. cox and f.r. pontet, j.nucl.energy 21,271 (1967) 525 1451 co69 j.a. cookson and j.g.locke,nucl.phys.a146,417(1970) 525 1451 co73 m.s. coates et al., priv. comm. to l.stewart (1973) 525 1451 da56 r.b.day,phys.rev.102,767 (1956) 525 1451 da60 r.b. day and m.walt,phys.rev.117,1330 (1960) 525 1451 da61 e.a. davis et al., nucl.phys.27,448 (1961) 525 1451 di67 k.m. diment, aere-r-5224 (1967) 525 1451 di88 j.k.dickens, proc.conf. on nuc.data for sci.& tech.,mito, 525 1451 japan (1988) p.213. 525 1451 fo61 d.m. fossan et al., phys.rev. 123,209 (1961) 525 1451 fr56 g.m. frye and j.h. gammel,phys.rev. 103,328 (1956) 525 1451 gl82 s.glendinning, nuc.sci.eng.80,256(1982) 525 1451 ha73 s.l.hausladen, thesis, ohio univ. coo-1717-5 (1973) 525 1451 he80 d.hetrick & c.y.fu, ornl/tm-7341 (1980). 525 1451 hy69 m.hyakutake, eandc(j)-13 (1969) p.29 525 1451 ho69 j.c. hopkins, priv. comm. lasl (1969) 525 1451 ir67 d.c.irving, ornl-tm-1872 (1967) 525 1451 ka87 R.Kavanagh & R.Marcley, Phys.Rev.C36, 1194 (1987). 525 1451 la71 r.o. lane et al., phys.rev.c4,380 (1971) 525 1451 ma68 r.l.macklin and j.h.gibbons,phys.rev.165,1147 (1968) 525 1451 mo66 f.p.mooring et al.,nucl.phys.82,16 (1966) 525 1451 ne54 n.g.nereson,la-1655 (1954) 525 1451 ne70 d.o.nellis et al., phys.rev. c1,847 (1970) 525 1451 po70 d.porter et al., awre o 45/70 (1970) 525 1451 qa85 S.Qaim et al., Santa Fe Conf. (1985)p.97. 525 1451 qa88 S.Qaim et al., Mito Conf. (1988) p.225. 525 1451 sa88 E.T. Sadowski, Ph.D thesis, Ohio U., (Nov.,1988). 525 1451 sc76 r.a. schrack et al., proc.icinn(erda-conf-760715-p2),1345 525 1451 (1976) 525 1451 se76 r.m. sealock and j.c. overley, phys.rev.c13,2149 (1976) 525 1451 si65 r.h.siemssen et al., nucl.phys.69,209 (1965) 525 1451 sp73 r.r. spencer et al., eandc(e)147,al (1973) 525 1451 te62 k.tesch, nucl.phys.37,412 (1962) 525 1451 th67 g.e. thomas et al., nucl.instr.meth.56,325 (1967) 525 1451 ts63 k.tsukada and o.tanaka,j.phys.soc.japan 18,610 (1963) 525 1451 va65 v.valkovic et al., phys.rev. 139,331 (1965) 525 1451 va70 b.vaucher et al.,helv.phys.acta 43,237 (1970) 525 1451 va72 l.van der zwan and k.w.geiger, nucl.phys. a180,615 (1972) 525 1451 wi55 h.b. willard et al., phys.rev. 98,669(1955) 525 1451 wy58 m.e. wyman et al., phys.rev.112,1264 (1958) 525 1451 **************************************************************** 525 1451 525 1451 525 1451 525 1451 525 1451 ***************** Program LINEAR (VERSION 2002-1) *************** 525 1451 For All Data Greater than 1.0000E-10 barns in Absolute Value 525 1451 Data Linearized to Within an Accuracy of .100000000 per-cent 525 1451 ***************** Program SIGMA1 (VERSION 2002-1) *************** 525 1451 Data Doppler Broadened to 300.000000 Kelvin 525 1451 for All Data Greater than 1.0000E-10 barns in Absolute Value 525 1451 Data Linearized to Within an Accuracy pf .100000000 per-cent 525 1451 ***************** Program FIXUP (Version 2002-1) **************** 525 1451 Corrected ZA/AWR in All Sections-----------------------------Yes 525 1451 Corrected Thresholds-----------------------------------------Yes 525 1451 Extended Cross Sections to 20 MeV----------------------------No 525 1451 Allow Cross Section Deletion---------------------------------No 525 1451 Allow Cross Section Reconstruction---------------------------No 525 1451 Make All Cross Sections Non-Negative-------------------------Yes 525 1451 Delete Energies Not in Ascending Order-----------------------Yes 525 1451 Deleted Duplicate Points-------------------------------------Yes 525 1451 Check for Ascending MAT/MF/MT Order--------------------------Yes 525 1451 Check for Legal MF/MT Numbers--------------------------------Yes 525 1451 Allow Creation of Missing Sections---------------------------No 525 1451 Allow Insertion of Energy Points-----------------------------No 525 1451 Create Uniform Energy Grid-----------------------------------No 525 1451 Delete Section if Cross Section =0 at All Energies-----------Yes 525 1451 **************************************************************** 525 1451 ***************** Program GROUPIE (VERSION 2002-1) ************** 525 1451 Unshielded Group Averages Using 640 Groups 525 1451 Weighting Spectrum: Flat (Constant) Spectrum 525 1451 1 451 263 2 525 1451 3 107 217 1 525 1451 33 107 26 1 525 1451 525 1 0 525 0 0 5.01000E+3 9.92692E+0 0 0 0 0 525 3107 2.78950E+6 2.78950E+6 0 0 1 641 525 3107 641 1 525 3107 .000100000 60369.5672 .000105000 58961.8482 .000110000 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2.243903-6 2.000165-6 52533107 1.927335-6 1.633085-6 1.490809-6 1.647004-6 1.200942-6 1.128964-6 52533107 2.552806-6 2.624028-6 2.350393-6 2.167907-6 2.540208-6 1.939686-6 52533107 1.230224-6 2.113235-6 1.424748-6 1.662929-6 2.916571-6 2.927420-6 52533107 3.121191-6 3.670394-6 2.363825-6 1.299338-6 2.929283-6 1.881633-6 52533107 2.253798-6 4.641171-6 6.294455-6 5.607427-6 2.930722-6 2.917079-6 52533107 4.089449-6 2.707325-6 2.287332-6 1.083199-5 1.198476-5 7.899932-6 52533107 5.246804-6 7.085706-6 4.943829-6 5.243390-6 2.019061-5 1.881386-5 52533107 8.922377-6 9.271985-6 7.711829-6 9.574556-6 2.834902-5 2.180783-5 52533107 7.471345-6 8.265557-6 6.775191-6 3.334345-5 1.719968-5 8.391731-6 52533107 6.705476-6 4.365900-5 1.552481-5 1.322365-5 4.232958-5 2.020522-5 52533107 1.222438-4 52533107 52533 0 525 0 0 0 0 0 9.01900E+3 1.88352E+1 0 0 34 10 925 1451 0.0 0.0 0 0 0 6 925 1451 1.00000E+0 3.00001E+7 0 0 10 2002 925 1451 3.00000E+2 0.0 1 0 164 3 925 1451 9-F - 19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 DIST-Feb2004 925 1451 ----IRDF-2002 MATERIAL 925 925 1451 -----INCIDENT NEUTRON DATA 925 1451 ------ENDF-6 FORMAT 925 1451 ***************************************************************** 925 1451 9-F -19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 DIST-JAN02 20020125 925 1451 ----BROND-2 MATERIAL 925 925 1451 -----INCIDENT NEUTRON DATA 925 1451 ------ENDF-6 FORMAT 925 1451 ------Russian Reactor Dosimetry File RRDF-2002 925 1451 ***************************************************************** 925 1451 Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko 925 1451 ***************************************************************** 925 1451 MF= 3 925 1451 MT= 16 -(n,2n) cross section data 925 1451 -------------------------------------- 925 1451 Excitation function for the F-19(n,2n)F-18 reaction in the 925 1451 energy region from threshold to 30 MeV was evaluated by means of 925 1451 statistical analysis of experimental cross section data [1-17] and 925 1451 data from GNASH [18,19] calculation. 925 1451 Experimental data [2-3],[5],[9-13],[15-17] were renormalized 925 1451 to the new standards for monitor reactions cross sections. Data 925 1451 of Mc Crary et al. [1], Rayburn et al.[2], Bormann et al.[4], and 925 1451 Shiokawa et al. [7] were renormalized to the results of precise 925 1451 measurements Vonach et al. [9] and Ikeda et al. [15] in the 14 MeV 925 1451 region. Data of Chatterjee et al. [8] were corrected to their pre- 925 1451 vious measurements at the 14.8 MeV point [6]. Results of measure- 925 1451 ments of Nagel [5] were taken only from SUBENT 005, EXFOR 20198. 925 1451 Experimental cross section data from ref. [20-31] were rejec- 925 1451 ted due to their big discrepancy with the main bulk of experimen- 925 1451 al data [1-17] and data from theoretical model calculation. 925 1451 The final procedure of evaluation F-19(n,2n)F-18 excitation 925 1451 function from threshold to 30 MeV has been carried out within the 925 1451 framework of generalized least squares method. Rational function 925 1451 was used as model function [32]. Calculations was performed by 925 1451 means of Pade-2 code [33]. 925 1451 U-235 thermal fission [34] and Cf-252 spontaneous fission 925 1451 neutron spectra [35] averaged cross-sections calculated from the 925 1451 evaluated F-19(n,2n)F-18 excitation function are the following: 925 1451 925 1451 ----------------------------------------------------------------- 925 1451 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 925 1451 ----------------------I-----------------I------------------------ 925 1451 U-235 neutron fission I 0.007299 I 0.007200+-0.001000 [36] 925 1451 I I 0.006509+-0.000300 [37] 925 1451 I I 0.008653+-0.000464 [38] 925 1451 ----------------------I-----------------I------------------------ 925 1451 CF-252 spont. fission I 0.01615 I 0.01628+-0.00054 [39] 925 1451 I I 0.01612+-0.00054 [40] 925 1451 ----------------------------------------------------------------- 925 1451 925 1451 MF=33 925 1451 MT= 16 -(n,2n) cross section cov. matrix 925 1451 --------------------------------------------- 925 1451 Uncertainties in the evaluated excitation function for the 925 1451 reaction F-19(n,2n)F-18 are given in the form of relative covari- 925 1451 ance matrix for the 26-neutron energy groups (LB=5). Covariance 925 1451 matrix of uncertainties was calculated simultaneously with 925 1451 recommended cross section data by means of PADE-2 code. 925 1451 Eigenvalues of the 6-th digits relative covariance matrix 925 1451 given in the 33-file are the following: 925 1451 925 1451 3.67622E-08 3.74071E-08 3.79051E-08 3.91111E-08 925 1451 4.11094E-08 4.32321E-08 4.68199E-08 4.98738E-08 925 1451 5.55426E-08 6.01322E-08 7.00100E-08 7.85485E-08 925 1451 9.57150E-08 1.06820E-07 1.28694E-07 1.47868E-07 925 1451 2.58858E-07 6.32301E-07 3.80384E-06 5.45023E-04 925 1451 1.36448E-03 3.28506E-03 8.26671E-03 1.39754E-02 925 1451 1.58981E-02 6.37025E-02 925 1451 925 1451 References : 925 1451 1. J.H.Mc Crary,I.L.Morgan Bull. American Phys. Soc., v.5, 925 1451 p.246, April 1960 ; 925 1451 J.H.Mc Crary,I.L.Morgan Report AFSWC-TR-60-30, 1960 925 1451 2. L.A.Rayburn Proc. of Conf. on Direct Interactions and Nuclear 925 1451 Reaction Mechanisms, Padua, 3-8 September 1962, Gordon and 925 1451 Breach, New York, 1963, p.322. ; 925 1451 L.A.Rayburn Bull. Am. Phys. Soc., v.7, p.335, April 1962 925 1451 3. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, Dec.1962 925 1451 4. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965 925 1451 5. W.Nagel EXFOR 20198.005, 1966 925 1451 6. A.Chatterjee et al. Progress Report BARC-305, p.30, Nov. 1967 925 1451 7. T.Shiokawa et al. J. Inorg. Nucl. Chem., v.30, p.1, Jan. 1968 925 1451 8. A.Chatterjee e.a. Proc.of Symposium Nucl.Phys. and Solid State 925 1451 Phys., Roorke, India, 1969, v.2, p.117, December 1969 925 1451 9. H.K.Vonach et al. Proc. of 2-nd Conference on Nuclear Cross- 925 1451 Sections and Technology, Washington D.C., 4-7 March 1968, v.2, 925 1451 p.885 925 1451 10. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 925 1451 11. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, April 1972 925 1451 12. J.C.Robertson et al. J. Nucl. Energ., v.27, p.531, Aug. 1973 925 1451 13. R.A.Sigg Dissert. Abstr., sect. B, v.37, p.2237, Nov. 1976 925 1451 14. T.B.Ryves et al. J. of Physics, pt.G, v.4, n.11, p.1783, 1978 925 1451 15. Y.Ikeda et al. Report JAERI-1312, 1988 925 1451 16. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 925 1451 17. C.L.Hartmann, P.M.DeLuca Nucl. Sci. Eng., v.109, p.319, 1991 925 1451 18. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 925 1451 Model Code for Calculation of Cross Section and Emission 925 1451 Spectra. Report LA-6947, Los Alamos, 1977 925 1451 19. E.L.Trykov, G.Ya.Tertychnyi Private communication, IPPE, 925 1451 Obninsk, May 1999 925 1451 20. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 925 1451 21. V.J.Ashby e.a. Phys. Rev., v.111, p.616, 1958 925 1451 22. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 925 1451 23. O.D.Brill et al. Doklady Akademii Nauk, v.136,n.1,p.55, 1961; 925 1451 O.D.Brill et al. Soviet Physics-Doklady, v.6, p.24, 1961 925 1451 24. J.Picard, C.F.Williamson Nucl. Phys., v.63, p.673, April 1965 925 1451 25. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 925 1451 26. J.Csikai Report EANDC-50 S, paper 102, July 1965 925 1451 27. A.Pasquarelli Nucl. Phys. A, v.93, p.218, March 1967 925 1451 28. M.Bormann, I.Riehle Zeitschrift f.Physik, v.207, p.64, 925 1451 October 1967 925 1451 29. H.O.Menlove et al. Phys. Rev., v.163, p.1308, 1967 925 1451 30. D.Crumpton J.Inorg. Nucl. Chem., v.31, p.3727, December 1969 925 1451 31. J.Araminowicz, J.Dresler Report INR-1464, p.14, May 1973 925 1451 32. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 925 1451 st's Meeting on Evaluation and Processing of Covariance Data, 925 1451 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 925 1451 33. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 925 1451 34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 925 1451 Library, MAT=9228, MF=5, MT=18, eval. April 1989 925 1451 35. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 925 1451 36. F.Nasyrov, B.D.Sciborskij Atomnaja Energija, v.25, no.5, 925 1451 p.437, November 1968 925 1451 37. M.Najzer, J.Rant Report IAEA-208, v.2, p.247, 1978 925 1451 38. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 925 1451 39. W.Mannhart Handbook on Nuclear Activation Data. IAEA Tech- 925 1451 nical Report series No.273, p.413, 1987 925 1451 40. W.Mannhart Validation of Differential Cross Sections with 925 1451 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 925 1451 September 2002 925 1451 ***************************************************************** 925 1451 File 2 added to the pointwise file containing only the effective 925 1451 scattering radius with no resonance parameters given. 925 1451 Taken from ENDF/B-VI 925 1451 925 1451 ***************************************************************** 925 1451 ***************** Program LINEAR (VERSION 2002-1) *************** 925 1451 For All Data Greater than 1.0000E-10 barns in Absolute Value 925 1451 Data Linearized to Within an Accuracy of .100000000 per-cent 925 1451 ***************** Program SIGMA1 (VERSION 2002-1) *************** 925 1451 Data Doppler Broadened to 300.000000 Kelvin 925 1451 for All Data Greater than 1.0000E-10 barns in Absolute Value 925 1451 Data Linearized to Within an Accuracy pf .100000000 per-cent 925 1451 ***************** Program FIXUP (Version 2002-1) **************** 925 1451 Corrected ZA/AWR in All Sections-----------------------------Yes 925 1451 Corrected Thresholds-----------------------------------------Yes 925 1451 Extended Cross Sections to 20 MeV----------------------------No 925 1451 Allow Cross Section Deletion---------------------------------No 925 1451 Allow Cross Section Reconstruction---------------------------No 925 1451 Make All Cross Sections Non-Negative-------------------------Yes 925 1451 Delete Energies Not in Ascending Order-----------------------Yes 925 1451 Deleted Duplicate Points-------------------------------------Yes 925 1451 Check for Ascending MAT/MF/MT Order--------------------------Yes 925 1451 Check for Legal MF/MT Numbers--------------------------------Yes 925 1451 Allow Creation of Missing Sections---------------------------No 925 1451 Allow Insertion of Energy Points-----------------------------No 925 1451 Create Uniform Energy Grid-----------------------------------No 925 1451 Delete Section if Cross Section =0 at All Energies-----------Yes 925 1451 ***************** Program GROUPIE (VERSION 2002-1) ************** 925 1451 Unshielded Group Averages Using 640 Groups 925 1451 Weighting Spectrum: Flat (Constant) Spectrum 925 1451 1 451 171 1 925 1451 3 16 34 1 925 1451 33 16 71 1 925 1451 925 1 0 925 0 0 9.01900E+3 1.88352E+1 0 0 0 0 925 3 16 -1.04322E+7-1.04322E+7 0 0 1 92 925 3 16 92 1 925 3 16 10900000.0 2.02752E-6 11000000.0 5.63229E-5 11100000.0 .000137655 925 3 16 11200000.0 .000292275 11300000.0 .000548721 11400000.0 .000917543 925 3 16 11500000.0 .001402145 11600000.0 .002002095 11700000.0 .002714490 925 3 16 11800000.0 .003534705 11900000.0 .004456885 12000000.0 .005474310 925 3 16 12100000.0 .006579685 12200000.0 .007765400 12300000.0 .009023740 925 3 16 12400000.0 .010347050 12500000.0 .011727850 12600000.0 .013159000 925 3 16 12700000.0 .014633700 12800000.0 .016152650 12900000.0 .017695750 925 3 16 13000000.0 .019265950 13100000.0 .020863250 13200000.0 .022460550 925 3 16 13300000.0 .024071763 13400000.0 .025696888 13500000.0 .027322013 925 3 16 13600000.0 .028947138 13700000.0 .030572263 13800000.0 .032197388 925 3 16 13900000.0 .033822513 14000000.0 .035447638 14100000.0 .037049625 925 3 16 14200000.0 .038628475 14300000.0 .040207325 14400000.0 .041786175 925 3 16 14500000.0 .043331888 14600000.0 .044844463 14700000.0 .046357038 925 3 16 14800000.0 .047869613 14900000.0 .049339675 15000000.0 .050767225 925 3 16 15100000.0 .052194775 15200000.0 .053622325 15300000.0 .054999450 925 3 16 15400000.0 .056326150 15500000.0 .057652850 15600000.0 .058979550 925 3 16 15700000.0 .060248850 15800000.0 .061460750 15900000.0 .062672650 925 3 16 16000000.0 .063884550 16100000.0 .065033000 16200000.0 .066118000 925 3 16 16300000.0 .067203000 16400000.0 .068288000 16500000.0 .069304550 925 3 16 16600000.0 .070252650 16700000.0 .071200750 16800000.0 .072148850 925 3 16 16900000.0 .073024838 17000000.0 .073828713 17100000.0 .074632588 925 3 16 17200000.0 .075436463 17300000.0 .076166188 17400000.0 .076821763 925 3 16 17500000.0 .077477338 17600000.0 .078132913 17700000.0 .078714000 925 3 16 17800000.0 .079220600 17900000.0 .079727200 18000000.0 .080233800 925 3 16 18100000.0 .080667413 18200000.0 .081028038 18300000.0 .081388663 925 3 16 18400000.0 .081749288 18500000.0 .082040025 18600000.0 .082260875 925 3 16 18700000.0 .082481725 18800000.0 .082702575 18900000.0 .082858125 925 3 16 19000000.0 .082948375 19100000.0 .083038625 19200000.0 .083128875 925 3 16 19300000.0 .083180900 19400000.0 .083152770 19500000.0 .083082710 925 3 16 19600000.0 .083012650 19700000.0 .082942590 19800000.0 .082872530 925 3 16 19900000.0 .082740370 20000000.0 0.0 925 3 16 925 3 0 925 0 0 9.01900E+3 1.88352E+1 0 0 0 1 92533 16 0.000000+0 0.000000+0 0 16 0 1 92533 16 0.000000+0 0.000000+0 1 5 406 28 92533 16 1.000000-5 1.090000+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7 92533 16 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7 92533 16 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7 92533 16 2.000000+7 2.100000+7 2.200000+7 2.300000+7 2.400000+7 2.500000+7 92533 16 2.700000+7 2.800000+7 2.900000+7 3.000000+7 0.000000+0 0.000000+0 92533 16 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 0.000000+0 7.844560-3 4.898350-3 3.027060-3 1.929170-3 1.321910-3 92533 16 9.926111-4 8.097050-4 6.990610-4 6.218640-4 5.596050-4 5.048120-4 92533 16 4.555230-4 4.121780-4 3.758470-4 3.473540-4 3.269110-4 3.140740-4 92533 16 3.073570-4 3.120960-4 3.231580-4 3.310920-4 3.298620-4 3.041000-4 92533 16 2.525070-4 2.039030-4 1.464150-4 3.648070-3 2.360540-3 1.449110-3 92533 16 9.104930-4 6.319380-4 5.059420-4 4.569550-4 4.388680-4 4.266530-4 92533 16 4.088340-4 3.819840-4 3.470900-4 3.071470-4 2.656870-4 2.259100-4 92533 16 1.902720-4 1.486420-4 1.141580-4 1.016320-4 1.039070-4 1.134800-4 92533 16 1.281520-4 1.350840-4 1.314670-4 1.212070-4 1.826270-3 1.354210-3 92533 16 9.782671-4 7.059900-4 5.267220-4 4.207220-4 3.665780-4 3.449020-4 92533 16 3.398810-4 3.397380-4 3.365240-4 3.256910-4 3.054490-4 2.760780-4 92533 16 2.392420-4 1.754770-4 8.900070-5 1.611170-5-3.205140-5-5.099350-5 92533 16 -2.365820-5 5.330250-5 1.291950-4 2.188860-4 1.233180-3 1.050650-3 92533 16 8.482810-4 6.625510-4 5.129570-4 4.047920-4 3.347390-4 2.952800-4 92533 16 2.776250-4 2.733860-4 2.755370-4 2.787900-4 2.796490-4 2.762050-4 92533 16 2.614270-4 2.288330-4 1.889520-4 1.513570-4 1.231830-4 1.085890-4 92533 16 1.236560-4 1.520640-4 1.922260-4 1.030240-3 9.309550-4 7.910340-4 92533 16 6.422140-4 5.056870-4 3.931520-4 3.093600-4 2.543630-4 2.252570-4 92533 16 2.174790-4 2.257800-4 2.449250-4 2.701550-4 3.105180-4 3.558030-4 92533 16 3.811660-4 3.836510-4 3.655150-4 3.091160-4 2.316670-4 1.739440-4 92533 16 1.144030-4 9.301140-4 8.611210-4 7.506000-4 6.229440-4 4.974770-4 92533 16 3.876710-4 3.015590-4 2.426370-4 2.107830-4 2.032840-4 2.157690-4 92533 16 2.430530-4 3.003160-4 3.817500-4 4.465680-4 4.803090-4 4.784630-4 92533 16 4.115300-4 2.889300-4 1.821310-4 6.207860-5 8.648120-4 8.135850-4 92533 16 7.261930-4 6.210140-4 5.137590-4 4.162000-4 3.360620-4 2.773020-4 92533 16 2.407400-4 2.248090-4 2.263440-4 2.532360-4 3.094430-4 3.658040-4 92533 16 4.035410-4 4.133410-4 3.692840-4 2.697090-4 1.753330-4 6.488820-5 92533 16 8.276580-4 7.994630-4 7.403910-4 6.622230-4 5.756870-4 4.895590-4 92533 16 4.102830-4 3.420170-4 2.868660-4 2.452630-4 2.075860-4 1.890180-4 92533 16 1.937990-4 2.070150-4 2.180840-4 2.167570-4 1.920930-4 1.606910-4 92533 16 1.194350-4 8.367870-4 8.381600-4 8.077220-4 7.513760-4 6.760250-4 92533 16 5.886680-4 4.958200-4 4.031020-4 3.150170-4 2.001340-4 8.278800-5 92533 16 1.074360-5-2.078540-5-2.009100-5 2.343720-5 9.478700-5 1.508320-4 92533 16 2.094530-4 9.030970-4 9.293760-4 9.163470-4 8.669560-4 7.869960-4 92533 16 6.839560-4 5.660230-4 4.412210-4 2.582200-4 4.586960-5-1.068070-4 92533 16 -1.912730-4-2.107930-4-1.358110-4 2.138250-5 1.612100-4 3.183170-4 92533 16 1.012600-3 1.049310-3 1.037800-3 9.812610-4 8.866920-4 7.633760-4 92533 16 6.215440-4 3.970180-4 1.170730-4-1.006010-4-2.340860-4-2.800390-4 92533 16 -1.974460-4 1.093280-5 2.077500-4 4.350440-4 1.136340-3 1.170610-3 92533 16 1.152160-3 1.086070-3 9.810220-4 8.476920-4 6.195350-4 3.158060-4 92533 16 6.329550-5-1.052330-4-1.794050-4-1.175480-4 9.273780-5 3.048660-4 92533 16 5.562250-4 1.254720-3 1.286290-3 1.267530-3 1.204830-3 1.107390-3 92533 16 9.184080-4 6.431870-4 3.946850-4 2.121830-4 1.124980-4 1.261560-4 92533 16 2.843660-4 4.638940-4 6.851270-4 1.376450-3 1.420770-3 1.422120-3 92533 16 1.386320-3 1.278440-3 1.085040-3 8.822720-4 7.106800-4 5.921990-4 92533 16 5.353610-4 5.914810-4 6.921020-4 8.298950-4 1.539830-3 1.622460-3 92533 16 1.669850-3 1.679580-3 1.616300-3 1.498950-3 1.363950-3 1.236560-3 92533 16 1.094900-3 1.009270-3 9.922760-4 1.001160-3 1.798240-3 1.944450-3 92533 16 2.099870-3 2.205700-3 2.207720-3 2.133310-3 2.009010-3 1.777510-3 92533 16 1.524740-3 1.362900-3 1.209860-3 2.198710-3 2.517890-3 2.820120-3 92533 16 2.967440-3 2.974120-3 2.866070-3 2.549010-3 2.119470-3 1.798830-3 92533 16 1.465550-3 3.093180-3 3.712880-3 4.106620-3 4.263970-3 4.206430-3 92533 16 3.790030-3 3.114020-3 2.560510-3 1.957740-3 4.741660-3 5.470710-3 92533 16 5.854090-3 5.903210-3 5.430360-3 4.514070-3 3.710880-3 2.809610-3 92533 16 6.497010-3 7.107000-3 7.299680-3 6.881850-3 5.882950-3 4.952680-3 92533 16 3.884000-3 7.920590-3 8.280630-3 8.031330-3 7.128890-3 6.218540-3 92533 16 5.143690-3 8.820440-3 8.840330-3 8.205440-3 7.459920-3 6.540140-3 92533 16 9.408330-3 9.443150-3 9.180490-3 8.759390-3 1.037760-2 1.080020-2 92533 16 1.110710-2 1.176100-2 1.264710-2 1.416170-2 92533 16 92533 0 925 0 0 0 0 0 1.10230E+4 2.27923E+1 0 0 34 101125 1451 0.0 0.0 0 0 0 61125 1451 1.00000E+0 2.00000E+7 0 0 10 20021125 1451 3.00000E+2 0.0 1 0 214 51125 1451 11-Na- 23 ORNL,TOH EVAL-DEC77 D. C. LARSON,S.IWASAKI 1125 1451 DIST-Feb2004 1125 1451 ----IRDF-2002 MATERIAL 1125 1125 1451 -----INCIDENT NEUTRON DATA 1125 1451 ------ENDF-6 FORMAT 1125 1451 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1125 1451 DOSIMETRY 1125 1451 ******************************************************************1125 1451 11-NA- 23 ORNL EVAL-DEC77 D. C. LARSON 1125 1451 DIST-SEP 1 REV1-JUL91 20010926 1125 1451 ----ENDF/B-VI MATERIAL 1125 REVISION 1 1125 1451 1125 1451 **************************************************************** 1125 1451 11-NA- 23 TOH EVAL-AUG96 S.IWASAKI 1125 1451 DIST-JUL98 1125 1451 ----JENDL/D-99 MATERIAL 1125 1125 1451 -----INCIDENT NEUTRON DATA 1125 1451 ------ENDF-6 FORMAT 1125 1451 1125 1451 NA-23 (N,2N) NA-22 (HALF-LIFE = 2.6019Y) 1125 1451 **************************************************************** 1125 1451 ================================================================ 1125 1451 ************** Start of ENDF/B-VI Bibliography ************** 1125 1451 ================================================================ 1125 1451 ENDF/B-VI MOD 2 Revision, September 2000, S.C.Frankle, R.C.Reedy,1125 1451 P.G.Young (LANL) 1125 1451 1125 1451 The secondary gamma-ray spectrum for radiative capture (MF 12, 1125 1451 MT 102) has been updated using new experimental data. 1125 1451 The previous evaluation (MOD 1: 61 gamma rays) is replaced with 1125 1451 292 discrete gamma rays based on thermal neutron experimental 1125 1451 data. Thermal spectrum assumed to 20 MeV. 1125 1451 The Q-value for radiative capture was also updated in File 3. 1125 1451 1125 1451 Gas production added as MF=3, MT=203,207 1125 1451 1125 1451 Details of these changes are described in Frankle et al. [Fr01]. 1125 1451 1125 1451 **************************************************************** 1125 1451 1125 1451 ENDF/B-VI MOD 1 Revision, July 1991, V. McLane (NNDC) 1125 1451 1125 1451 REVISION 1 CORRECTION 1125 1451 1125 1451 Corrected number of energy ranges in File 32, MT = 151 to be 1. 1125 1451 1125 1451 **************************************************************** 1125 1451 1125 1451 ENDF/B-VI MOD 0, January 1990 (NNDC) 1125 1451 1125 1451 ENDF/B-V Material 1311 converted to ENDF-6 format by NNDC. 1125 1451 1125 1451 **************************************************************** 1125 1451 1125 1451 ENDF/B-V Evaluation, December 1977, D. C. Larson (ORNL) 1125 1451 1125 1451 MF=2 1125 1451 Resonance parameters are used from 600 eV to 500 keV. The 1125 1451 thermal capture cross section is given as 528 mb, in agreement 1125 1451 with the experimental results of 526.9+-4.5 mb [RY71], as well 1125 1451 as earlier results summarized in [RY71]. Using resonance 1125 1451 parameters E=2.81 keV, GN=376 eV, and GG=0.353 eV for the large 1125 1451 2.81 keV resonance gives the correct thermal capture value using 1125 1451 a Breit-Wigner shape, and this form is used to calculate the 1125 1451 capture crposs section from 1.0E-5 to 600 eV. The capture 1125 1451 width GG=0.353 eV is consistent with a recent result by Wilson 1125 1451 [WI77] where they find 0.24