7-N - 14 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 7.01400E+3 1.38827E+1 0 0 0 5 725 1451 1 0.0 0.0 0 0 0 6 725 1451 2 1.00000E+0 1.50000E+8 8 0 10 6 725 1451 3 0.0 0.0 1 0 572 111 725 1451 4 7-N - 14 LANL EVAL-JUN97 M.B.CHADWICK & P.G.YOUNG 725 1451 5 Ch97,Ch99 DIST-SEP 1 REV4- 20010926 725 1451 6 ----ENDF/B-VI MATERIAL 725 REVISION 3 725 1451 7 -----INCIDENT NEUTRON DATA 725 1451 8 ------ENDF-6 FORMAT 725 1451 9 725 1451 10 **************************************************************** 725 1451 11 725 1451 12 ENDF/B-VI MOD 5 Revision, May 2000, S.C.Frankle, R.C.Reedy, 725 1451 13 P.G.Young (LANL) 725 1451 14 725 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 725 1451 16 MT 102) has been updated for new experimental data at incident 725 1451 17 neutron energies up to 400 keV. The Q-value for radiative capture 725 1451 18 was also updated in File 3. Details of these changes are 725 1451 19 described in Frankle et al. [Fr01]. 725 1451 20 725 1451 21 The Legendre coefficients in MF=14, MT=102 were corrected by 725 1451 22 dividing each coefficient by 2L+1. 725 1451 23 725 1451 24 ****************************************************************** 725 1451 25 725 1451 26 ENDF/B-VI MOD 4 Evaluation, August 1997, M.B. Chadwick and 725 1451 27 P.G. Young (LANL) 725 1451 28 725 1451 29 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 725 1451 30 in cooperation with ECN Petten. 725 1451 31 725 1451 32 This evaluation provides a complete representation of the 725 1451 33 nuclear data needed for transport, damage, heating, 725 1451 34 radioactivity, and shielding applications over the incident 725 1451 35 neutron energy range from 1.0E-11 to 150 MeV. The discussion 725 1451 36 here is divided into the region below and above 20 MeV. 725 1451 37 725 1451 38 INCIDENT NEUTRON ENERGIES < 20 MeV 725 1451 39 Below 20 MeV the evaluation is based completely on the ENDF/B- 725 1451 40 VI.3 (Release 3) evaluation by P. G. Young, G. M. Hale, and M. 725 1451 41 B. Chadwick [Yo94]. 725 1451 42 725 1451 43 INCIDENT NEUTRON ENERGIES > 20 MeV 725 1451 44 The ENDF/B-VI Release 3 evaluation of n + 14N data extends to 725 1451 45 40 MeV and includes cross sections and energy-angle data for all 725 1451 46 significant reactions. The present evaluation utilizes a more 725 1451 47 compact composite reaction spectrum representation of the data 725 1451 48 above 20 MeV in order to reduce the length of the file, and we 725 1451 49 have only included the ENDF/B-VI data below 20 MeV. To avoid 725 1451 50 redundancy, the sections MT=78-90 are removed, since their 725 1451 51 thresholds lie between 20 and 40 MeV. No essential data for 725 1451 52 applications is lost with our representation above 20 MeV. 725 1451 53 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 725 1451 54 all reaction data. Production cross sections and emission 725 1451 55 spectra are given for neutrons, protons, deuterons, tritons, 725 1451 56 alpha particles, gamma rays, and all residual nuclides produced 725 1451 57 (A>5) in the reaction chains. To summarize, the ENDF sections 725 1451 58 with non-zero data above En = 20 MeV are: 725 1451 59 725 1451 60 MF=3 MT= 1 Total Cross Section 725 1451 61 MT= 2 Elastic Scattering Cross Section 725 1451 62 MT= 3 Nonelastic Cross Section 725 1451 63 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 725 1451 64 725 1451 65 MF=4 MT= 2 Elastic Angular Distributions 725 1451 66 725 1451 67 MF=6 MT= 5 Production Cross Sections and Energy-Angle 725 1451 68 Distributions for Emission Neutrons, Protons, 725 1451 69 Deuterons, Tritons, and Alphas; and Angle- 725 1451 70 Integrated Spectra for Gamma Rays and Residual 725 1451 71 Nuclei That Are Stable Against Particle Emission 725 1451 72 725 1451 73 The evaluation is based on nuclear model calculations that have 725 1451 74 been benchmarked to experimental data, especially for n + 14N 725 1451 75 and p + 14N reactions [Ch97]. We use the GNASH code system 725 1451 76 [Yo92], which utilizes Hauser-Feshbach statistical, 725 1451 77 preequilibrium and direct-reaction theories. Spherical optical 725 1451 78 model calculations are used to obtain particle transmission 725 1451 79 coefficients for the Hauser-Feshbach calculations, as well as 725 1451 80 for the elastic neutron angular distributions. 725 1451 81 Cross sections and spectra for producing individual residual 725 1451 82 nuclei are included for reactions. The energy-angle-correlations 725 1451 83 for all outgoing particles are based on Kalbach systematics 725 1451 84 [Ka88]. 725 1451 85 A model was developed to calculate the energy distributions of 725 1451 86 all recoil nuclei in the GNASH calculations [Ch96]. The recoil 725 1451 87 energy distributions are represented in the laboratory system in 725 1451 88 MT=5, MF=6, and are given as isotropic in the lab system. All 725 1451 89 other data in MT=5,MF=6 are given in the center-of-mass system. 725 1451 90 This method of representation utilizes the LCT=3 option approved 725 1451 91 at the November, 1996, CSEWG meeting. 725 1451 92 Preequilibrium corrections were performed in the course of the 725 1451 93 GNASH calculations using the exciton model of Kalbach [Ka77], 725 1451 94 [Ka85], validated by comparison with calculations using Feshbach, 725 1451 95 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 725 1451 96 nuclear data sheets were matched to continuum level densities 725 1451 97 using the formulation of Ignatyuk [Ig75] and pairing and shell 725 1451 98 parameters from the Cook [Co67] analysis. Neutron and charged- 725 1451 99 particle transmission coefficients were obtained from the 725 1451 100 optical potentials, as discussed below. Gamma-ray transmission 725 1451 101 coefficients were calculated using the Kopecky-Uhl model [Ko90]. 725 1451 102 725 1451 103 DETAILS OF THE n + 14N ANALYSIS 725 1451 104 GNASH calculations [Yo92,Ch94] were performed for neutron and 725 1451 105 proton reactions on nitrogen up to 150 MeV, and the calculated 725 1451 106 results were benchmarked against experimental data. For neutrons 725 1451 107 below 100 MeV, the present evaluation made extensive use of our 725 1451 108 previous work [Ch96a]. Very minor differences with this earlier 725 1451 109 work exist due to recent developments in the GNASH code. Much use 725 1451 110 was made of measured data in the evaluation, since an accurate 725 1451 111 modeling of reactions on a light nucleus is difficult. In this 725 1451 112 way we were able to obtain a fairly good description of the 725 1451 113 emission spectra of secondary particles and gamma rays. 725 1451 114 Additionally, the (angle-integrated) emission spectra of heavy 725 1451 115 recoils were calculated using our model described in Ref. [Ch96]. 725 1451 116 Some additional information on this evaluation can be found in 725 1451 117 Ref. [Ch97]. 725 1451 118 Between 20 and 150 MeV, the optical models used (the neutron 725 1451 119 potential of Islam below 60 MeV [Is88]; Madland's potential 725 1451 120 [Ma88] at higher energies, with Lane transformations for the 725 1451 121 proton potential) provided a reasonably good description of 725 1451 122 measured reaction cross section data. But since a very accurate 725 1451 123 description of the reaction cross section is important for 725 1451 124 determining secondary particle spectra, we slightly modify the 725 1451 125 calculated results to better describe the experimental data, and 725 1451 126 renormalize the calculated transmission coefficients accordingly. 725 1451 127 The SCAT2 code [Be92] was used to calculate the transmission 725 1451 128 coefficients. No measurements for the neutron reaction cross 725 1451 129 section on nitrogen exist above about 50 MeV. However, 725 1451 130 systematics have been determined from a number of target elements 725 1451 131 at 95 MeV by DeJuren [De50], and for 100 MeV protons by Kirby and 725 1451 132 Link [Ki66] (at this energy the proton and neutron reaction cross 725 1451 133 sections would be expected to be very similar). We have, 725 1451 134 therefore, used these systematics to guide our evaluated reaction 725 1451 135 cross sections. Additionally, below 50 MeV we have also been 725 1451 136 guided by the proton-induced reaction cross sections of Carlson 725 1451 137 et al. [Ca75]. Experimental total elastic scattering values of 725 1451 138 Islam et al. [Is88], Olsson et al. [Ol90], and Petler et al. 725 1451 139 [Pe85] were obtained by subtracting their angle-integrated 725 1451 140 elastic data from the evaluated total cross sections (see below). 725 1451 141 The evaluated total cross section was obtained by slightly 725 1451 142 modifying the optical model results to agree with data, 725 1451 143 principally the new high-accuracy results of Finlay et al. 725 1451 144 [Fi93]. We use the ENDF/B-VI total cross section below 40 MeV 725 1451 145 recently evaluated by Young [Yo94]. 725 1451 146 Preequilibrium spectra for incident energies below 100 MeV were 725 1451 147 taken from our previous work [Ch96], where they were evaluated 725 1451 148 from a combination of FKK calculations [Ch93], and measured 725 1451 149 emission spectra data, while ensuring that unitarity is conserved 725 1451 150 (i.e., making sure the sum of primary emitted preequilibrium 725 1451 151 spectra does not exceed the reaction cross section). This 725 1451 152 approach has the advantage of facilitating a good representation 725 1451 153 of emission spectra experimental data. However, the lack of such 725 1451 154 data above 100 MeV prohibits its extension to higher energies, 725 1451 155 and therefore above 100 MeV, exciton model calculations were 725 1451 156 utilized from the GNASH code [Ka77, Ka85]. This results in some 725 1451 157 (small) discontinuities around 100 MeV in the production cross 725 1451 158 sections, though the impact of this is negligible for most 725 1451 159 applications. 725 1451 160 Nuclear level densities were determined using the Ignatyuk 725 1451 161 model [Ig75], as implemented by Arthur et al. [Yo92]. Pairing 725 1451 162 energies were obtained from the Cook systematics with the Los 725 1451 163 Alamos extensions to light nuclei from [Ar83]. This continuum 725 1451 164 level density formulation is matched continuously onto discrete 725 1451 165 low-lying levels at the lower excitation energies. Discrete level 725 1451 166 information (energy, spin, parity, gamma-ray branching ratios) is 725 1451 167 tabulated for each nuclide in an input file, which is based on 725 1451 168 the Ajzenberg-Selove compilations. For each nucleus we performed 725 1451 169 a level-density analysis and determined the excitation energy at 725 1451 170 which we judged the level data complete. Gamma-ray transmission 725 1451 171 coefficients were obtained from the Kopecky-Uhl model [Ko90]. 725 1451 172 An important test of the accuracy of the data libraries is that 725 1451 173 the evaluated emission spectra of light particles (A < 5) should 725 1451 174 be consistent with the measurements by Subramanian et al. of UC- 725 1451 175 Davis [Su86]. We have compared our calculated (lab frame) angle- 725 1451 176 integrated emission spectra of protons, deuterons, and alphas, 725 1451 177 with these measurements, with good agreement. The structure seen 725 1451 178 at high emission energies is due to the inclusion of discrete 725 1451 179 nuclear levels in our calculations. Also, kerma factors obtained 725 1451 180 from the evaluated cross sections are in fairly good agreement 725 1451 181 with experimental data [Ch96]. 725 1451 182 725 1451 183 **************************************************************** 725 1451 184 725 1451 185 ENDF/B-VI MOD 3 Revision, August 1994, P.G. Young (LANL) 725 1451 186 725 1451 187 This modification corrects the elastic and inelastic cross 725 1451 188 sections (MT=63-90) at incident neutron energies above 13.5.MeV 725 1451 189 given in MOD 2 of ENDF/B-VI. This correction was made to 725 1451 190 improve agreement with elastic scattering measurements up to 725 1451 191 25 MeV. The elastic neutron angular distributions above 20 MeV 725 1451 192 were also improved over the earlier data distributed in MOD 2, 725 1451 193 based upon fits to experimental data. 725 1451 194 725 1451 195 **************************************************************** 725 1451 196 725 1451 197 ENDF/B-VI MOD 2 Evaluation, September 1992, P.G. Young (LANL) 725 1451 198 725 1451 199 Extension to 40 MeV 725 1451 200 The modified version of the ENDF/B-VI evaluation created for 725 1451 201 DNA (described below) is extended in energy to 40 MeV. This ext- 725 1451 202 tension was accomplished using experimental data and the 9/92 725 1451 203 Version of the GNASH code, which was updated for higher energy 725 1451 204 calculations. More details will be given in a later progress 725 1451 205 report. 725 1451 206 The ENDF/B-VI evaluation was modified for DNA use to include 725 1451 207 results from Hale's R-matrix analysis that include Harvey's new 725 1451 208 total cross section measurement. These results are interim until 725 1451 209 we can incorporate the new ORNL scattering data. The ORNL 725 1451 210 preliminary scattering results confirm the parity of the first 725 1451 211 resonance as being positive, as used in the R-matrix analysis. 725 1451 212 725 1451 213 **************************************************************** 725 1451 214 725 1451 215 ENDF/B-VI MOD 1 Evaluation, May 1990, P.G. Young, G.M. Hale, 725 1451 216 M.B. Chadwick (LANL) 725 1451 217 725 1451 218 N14 free atom evaluation 725 1451 219 725 1451 220 GENERAL COMMENTS: 725 1451 221 The ENDF/B-VI data file for N14 is an essentially complete new 725 1451 222 evaluation. Below 2.5 MeV, it consists of an R-matrix analysis of 725 1451 223 the available experimental total, elastic, (n,p0), and (n,alpha0) 725 1451 224 cross sections and angular distributions using the EDA coupled- 725 1451 225 channel r-matrix code. At higher energies, the evaluation 725 1451 226 is an update of the 1972 evaluation of Young and Foster [Yo72] 725 1451 227 to include new experimental data since that time. More details 725 1451 228 of the evaluation are included below. 725 1451 229 725 1451 230 MF=2 ------------------------------------------------------------ 725 1451 231 725 1451 232 MT=451 No Resonance Parameters. Scattering Radius =8.86366-13 cm 725 1451 233 725 1451 234 MF=3 ------------------------------------------------------------ 725 1451 235 725 1451 236 THERMAL (2200 M/S) CROSS SECTIONS 725 1451 237 TOTAL 11.8135 B (N,GAMMA) 0.075 B 725 1451 238 ELASTIC 9.9114 B (N,P) 1.8271 B 725 1451 239 NONELASTIC 1.9021 B 725 1451 240 725 1451 241 MT=1 Total Cross Section 725 1451 242 Zero to 2.2 MeV, SIGT is obtained from sum of elastic, (n,p0), 725 1451 243 (n,a0) cross sections from r-matrix analysis, plus the (n,g) 725 1451 244 cross section described below. The coupled-channel r-matrix 725 1451 245 analysis was performed with the EDA code, fitting simultane- 725 1451 246 ously almost all available total, (n,n), (n,p0), and (n,a0) 725 1451 247 exp. data. The most important total cross section used were 725 1451 248 [Me49,Bi59,Bi69] at lower energies, and [Ca70,He70,Fo71] 725 1451 249 at higher energies. Significant shape difference found in 725 1451 250 the 0.1 - 20 keV region as compared to ENDF/B-V. 725 1451 251 2.2 MeV to 20 MeV, from [Ca70,He70,Fo71] using Ca70 alone 725 1451 252 at sharp resonances. Smoothed by appropriate fits, log-log 725 1451 253 interpolations is good to 1.3 pct to 0.4 MeV, linear inter- 725 1451 254 polation is good to 0.5 pct from 0.4 to 20 MeV, absolute 725 1451 255 error less than 1 pct above 2.2 MeV. Minor changes made in 725 1451 256 ENDF/V.2 evaluation in certain regions of high structure. 725 1451 257 MT=2 Elastic Scattering Cross Section 725 1451 258 Zero to 2.2 MeV, based upon r-matrix analysis described 725 1451 259 above. Experimental elastic angular distributions in analysis 725 1451 260 were [Fo55,Jo66]. 725 1451 261 2.2 to 20 MeV, based upon data of [Ch61,Ba67,St61,Ba63,Fo55, 725 1451 262 Jo66,Ph61,Be66,Lu67] and, especially, [Ch86,Te85,Ba85,Pe85, 725 1451 263 Pe74, Ne72]. Nonelastic cross sections were adjusted somewhat 725 1451 264 to achieve agreement with elastic data. 725 1451 265 MT=4 Sum of MT=51-82 Cross Sections. 725 1451 266 MT=16 (N,2N) Based on [Fe60,Br61,Bo65,Pr60]. 30% error estimated 725 1451 267 MT=51-62 Discrete Inelastic, Including N,Np Decay (LR=28) 725 1451 268 Threshold to 20 MeV. From (n,ngamma) data of [Di70,Or69,Cl69, 725 1451 269 Bu71,Ny71,Co68,Ha59,Be70,Di73] and, especially, [Ne89, 725 1451 270 Ro74,Ne72,Au86], together with the (n,n') data of [Ch86, 725 1451 271 Pe74,Ba63,Ba85,Ta87]. The level decay scheme of [Aj86] 725 1451 272 was used to interpret the (n,ngamma) data. 725 1451 273 MT=63-90 Inelastic Assuming Energy Bands Centered Around 725 1451 274 the Excitation Energies Chosen. Note that N,Np (LR=28) and 725 1451 275 n,nalpha (LR=22) decay are included and labeled. The cross 725 1451 276 sections are adjusted by differencing between total and 725 1451 277 nonelastic. Cross sections to the bands based on Hauser- 725 1451 278 Feshbach and nuclear temperature calculations. 725 1451 279 MT=102 Radiative Capture 725 1451 280 Zero to 0.25 MeV, 1/v from 75 mb(+-10pct) at thermal [Ju63]. 725 1451 281 0.25 to 1 MeV, transition region. 725 1451 282 1 to 20 MeV, deduced from N14(p,gamma)O15 data of [Ku70], 725 1451 283 assuming charge independence. Energy scale adjusted to match 725 1451 284 foot-hills of (p,gamma) giant resonance to resonance clusters 725 1451 285 served in N15 compound nucleus. 725 1451 286 MT=103 Sum of MT=600-606 Cross Sections. 725 1451 287 MT=104 Sum OF MT=650-653 Cross Sections. 725 1451 288 MT=105 SUM OF MT=700-701 Cross Sections. 725 1451 289 MT=107 Sum OF MT=800-810 Cross Sections. 725 1451 290 MT=108 (N,2ALPHA) Cross Section. 725 1451 291 Based on [Li52,Mo67] and Hauser-Feshbach calculation. 725 1451 292 MT=600 (N,P) Cross Section to C14 Ground State. 725 1451 293 Zero to 2.2 MeV, taken from coupled-channel r-matrix analysis. 725 1451 294 R-Matrix analysis based on [Jo50,Ga59], and esp. [Mo79]. 725 1451 295 2.2 to 13 MeV, based mainly on [Mo79] and inverse reaction data 725 1451 296 of [Wo67]. 725 1451 297 13 to 20 MeV, smooth extrapolation. 725 1451 298 MT=601-606 (n,p) Cross Sections to C14 Excited States. 725 1451 299 Thres. to 20 MeV, from (n,pgamma) data of [Or69,Di70,Cl69,Bu71, 725 1451 300 Ny71,Ro74]. 725 1451 301 MT=650 (N,D) Cross Section to C13 Ground State. 725 1451 302 Thres.to 15 MeV, from inverse cross section data of [Ch61,Be63] 725 1451 303 Near Thres.and direct data of [Mi68,Fe67,Ca57,Za63] at 14 MeV 725 1451 304 Plus the (n,dgamma) data of [Ro74,Ne89]. 725 1451 305 15 to 20 MeV, smooth extrapolations. 725 1451 306 MT=651-653 (n,d) Cross Section to Excited C13 Levels. 725 1451 307 Thres. to 20 MeV, direct data of [Fe67,Za63,Ca57], and 725 1451 308 (n,dgamma) data of [Or69, Di70, Ro74, Ne89]. 725 1451 309 MT=700-701 (N,T) Cross Sections to C12 Ground and 4.439 MeV Ex- 725 1451 310 cited State. 725 1451 311 Thres. to 15 MeV, direct data of [Ga59,Sc66,Re67,Fe67]. 725 1451 312 15 to 20 MeV, smooth extrapolations. 725 1451 313 MT=800-810 (n,alpha) Cross Section to Discrete B11 States. 725 1451 314 Thres. to 2.2 MeV, taken from coupled-channel r-matrix analysis 725 1451 315 direct (n,alpha) data included [Jo50,Ga59,Sc66] but the 725 1451 316 analysis mainly relied on Mo79. 725 1451 317 6 to 20 MeV, Used above direct data, together with (n,agamma) 725 1451 318 data of [Ha59,Di70,Or69,Ny71,Bu71,Be70,Cl68] and, especially, 725 1451 319 the data of [Ne89,Ro74]. Near En=14 MeV, the direct (n,a) 725 1451 320 data of [Li52,Ba68,Le68,Ma68] were also used. 725 1451 321 725 1451 322 MF=4 ------------------------------------------------------------ 725 1451 323 725 1451 324 MT=2 Elastic Angular Distributions. 725 1451 325 Zero to 2.2 mev, based upon r-matrix analysis described 725 1451 326 above. Experimental elastic angular distributions in analysis 725 1451 327 were [Fo55, Jo66]. 725 1451 328 2.2 TO 20 MeV, based upon data oF [Ch61,Ba67,St61,Ba63,Fo55, 725 1451 329 Jo66,Ph61,Be66,Lu67] and, especially, [Ch86,Te85,Ba85,Pe85, 725 1451 330 Pe74,Ne72]. 725 1451 331 MT=16 Angular Distribution for (n,2n) Reaction 725 1451 332 In the absence of data, isotropy in the cm system is assumed, 725 1451 333 and the corresponding 3-body phase-space is transformed to 725 1451 334 the lab system. For any reasonable cm distribution 725 1451 335 the strong forward peaking of the transformation will 725 1451 336 dominate. Normalized for trapezoidal integration. 725 1451 337 identical to ENDF/B-V. 725 1451 338 MT=51 to 62 Angular Distributions for Inelastic Scattering 725 1451 339 based mainly on (n,n') data of [Ch86], but the data of [Pe74, 725 1451 340 Ta87,Ba63,Bo61,Ba85] were used as well. 725 1451 341 above 7 MeV also used proton data of [Do64,Ha70,Od60] 725 1451 342 assuming charge symmetry, and neutron data of [Ba63]. 725 1451 343 threshold shapes modeled after Hauser-Feshbach calcs. 725 1451 344 MT=63-90 Angular Distributions for Inelastic Scattering. 725 1451 345 Assumed isotropic in cm at all energies. 725 1451 346 725 1451 347 MF=5 ------------------------------------------------------------ 725 1451 348 725 1451 349 MT=16 Spectrum of (N,2N) Secondary Neutrons 725 1451 350 in the absence of data, only the 3-body phase-space distribu- 725 1451 351 tion is given. Normalized for trapezoidal integration. 725 1451 352 identical to ENDF/B-V. 725 1451 353 725 1451 354 MF=12 ----------------------------------------------------------- 725 1451 355 725 1451 356 MT=102 (N,GAMMA) Multiplicities (same as ENDF/B-V) 725 1451 357 Zero to 0.25 MeV, thermal spectrum based primarily upon mea- 725 1451 358 surements of [Th67,Jo69,Gr68,Mo62]. 725 1451 359 .25 to 1 MeV, transition region where thermal spectrum is 725 1451 360 phased into single ground-state transition. 725 1451 361 1 to 20 MeV, deduced from N14(P,G)O15 data of [Ku70], who 725 1451 362 observed no significant transitions except to ground state. 725 1451 363 *** Note that gamma rays from N14(n,gamma,n') reactions are 725 1451 364 included under MT=102 rather than MT=4. This produces 725 1451 365 error messages when the checking code PSYCHE is run because 725 1451 366 there is an apparent violation of energy conservation. 725 1451 367 However, total energy is still conserved when MT=102 and 725 1451 368 and MT=4 are considered together. 725 1451 369 725 1451 370 MF=13 ----------------------------------------------------------- 725 1451 371 725 1451 372 All (N,XG) cross sections agree with the excitation cross 725 1451 373 sections in MF=3 via the relevant decay scheme [Aj80,Aj86]. 725 1451 374 *** Note that gamma-ray production cross sections are not 725 1451 375 included for MT=16. The reason is that all excited 725 1451 376 states in N13 are unstable to particle emission and 725 1451 377 the gamma-ray cross sections are negligibly small. 725 1451 378 725 1451 379 MT=4 (N,NG) Cross Section 725 1451 380 From data of [Ha59,Di70,Or69,Cl69,Bu71,Ny71,Co68,Be70,Di73], 725 1451 381 and especially, [Ne89,Ro74,Ne72,Au86] together with the 725 1451 382 (N,N') data of [Ch86,Pe74,Ba63,Ba85,Ta87] and the level 725 1451 383 decay scheme of [Aj86]. 725 1451 384 MT=28 (N,NPG) Cross Section 725 1451 385 From data OF [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73], 725 1451 386 after subtraction of MF=13,MT=103 data. 725 1451 387 MT=32 (N,NAG) Cross Section 725 1451 388 From data of [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73], 725 1451 389 after subtraction of MF=13,MT=107 data. 725 1451 390 MT=103 (N,PG) Cross Section 725 1451 391 From data of [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73]. 725 1451 392 MT=104 (N,DG) Cross Section 725 1451 393 From data of [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73], 725 1451 394 and estimates of MF=3,MT=651-653. 725 1451 395 MT=105 (N,TG) Cross Section 725 1451 396 (N,TG) estimated from (n,t) as discussed under MF=3,MT=741, 725 1451 397 and from (N,XG) data (see list below for MT=107). 725 1451 398 MT=107 (N,AG) Cross Section 725 1451 399 From (N,A) data of [Ga59,Sc66,Mo79] and (N,AG) data of 725 1451 400 [Ha59,Ny71,Or69,Bu71,Di70,Di73,Cl68,Co68] and esp. [Ne89, 725 1451 401 Ro74,Ne72]. Level decay scheme of [Aj80] was used. 725 1451 402 725 1451 403 MF=14 ----------------------------------------------------------- 725 1451 404 725 1451 405 Data on 9 strongest lines from inelastic scatt. and particle 725 1451 406 reactions taken from [Mo64] -- same as ENDF/B-V. 725 1451 407 MT=4 Inel. Scatt. to N14, 1.63 and 4.91 MeV Anistropic 725 1451 408 MT=102 (N,GAMMA) Angular Distributions. 725 1451 409 Zero to 0.4 MeV, all photons are isotropic. 725 1451 410 .4 to 20 MeV, anisotropic distribution for the single ground 725 1451 411 State transition is based upon N14(P,Go)O15 data by [Ku70]. 725 1451 412 MT=103 (N,P) to C14, all isotropic. 725 1451 413 MT=104 (N,NP)+(N,D) to C13, 3.85 MeV anisotropic 725 1451 414 MT=105 (N,ND)+(N,T) to C12, all isotropic 725 1451 415 MT=107 (N,ALPHA) to B11, all isotropic 725 1451 416 725 1451 417 MF=33 ----------------------------------------------------------- 725 1451 418 725 1451 419 To be provided at a later date. 725 1451 420 725 1451 421 ***************************************************************** 725 1451 422 725 1451 423 REFERENCES 725 1451 424 725 1451 425 [Aj80] F. Ajzenberg-Selove and C. Busch, Nucl.Phys.A 336, 1 725 1451 426 (1980) 725 1451 427 [Aj86] F. Ajzenberg-Selove, Nucl.Phys.A 449, 1 (1986) 725 1451 428 [Ar83] E.D. 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Maxson, Phys.Rev. 129, 1728 (1963) 725 1451 555 725 1451 556 ************************ C O N T E N T S *********************** 725 1451 557 ***************** Program LINEAR (VERSION 2004-1) *************** 725 1451 558 For All Data Greater than 1.0000E-10 barns in Absolute Value 725 1451 559 Data Linearized to Within an Accuracy of .100000000 per-cent 725 1451 560 ***************** Program FIXUP (Version 2004-1) **************** 725 1451 561 Corrected ZA/AWR in All Sections-----------------------------Yes 725 1451 562 Corrected Thresholds-----------------------------------------No 725 1451 563 Extended Cross Sections to 20 MeV----------------------------No 725 1451 564 Allow Cross Section Deletion---------------------------------No 725 1451 565 Allow Cross Section Reconstruction---------------------------Yes 725 1451 566 Make All Cross Sections Non-Negative-------------------------Yes 725 1451 567 Delete Energies Not in Ascending Order-----------------------Yes 725 1451 568 Deleted Duplicate Points-------------------------------------Yes 725 1451 569 Check for Ascending MAT/MF/MT Order--------------------------Yes 725 1451 570 Check for Legal MF/MT Numbers--------------------------------Yes 725 1451 571 Allow Creation of Missing Sections---------------------------No 725 1451 572 Allow Insertion of Energy Points-----------------------------No 725 1451 573 Create Uniform Energy Grid-----------------------------------No 725 1451 574 Delete Section if Cross Section =0 at All Energies-----------Yes 725 1451 575 **************** Program DICTIN (VERSION 2004-1) **************** 725 1451 576 1 451 687 5 725 1451 577 2 151 4 1 725 1451 578 3 1 544 4 725 1451 579 3 2 289 4 725 1451 580 3 4 74 3 725 1451 581 3 5 12 4 725 1451 582 3 16 11 2 725 1451 583 3 51 23 2 725 1451 584 3 52 39 2 725 1451 585 3 53 35 2 725 1451 586 3 54 28 2 725 1451 587 3 55 35 2 725 1451 588 3 56 36 2 725 1451 589 3 57 30 2 725 1451 590 3 58 23 2 725 1451 591 3 59 23 2 725 1451 592 3 60 26 2 725 1451 593 3 61 19 2 725 1451 594 3 62 18 2 725 1451 595 3 63 26 3 725 1451 596 3 64 24 3 725 1451 597 3 65 22 3 725 1451 598 3 66 22 3 725 1451 599 3 67 22 3 725 1451 600 3 68 20 3 725 1451 601 3 69 19 3 725 1451 602 3 70 19 3 725 1451 603 3 71 18 3 725 1451 604 3 72 16 3 725 1451 605 3 73 14 3 725 1451 606 3 74 12 3 725 1451 607 3 75 10 3 725 1451 608 3 76 8 3 725 1451 609 3 77 6 3 725 1451 610 3 102 119 5 725 1451 611 3 103 252 2 725 1451 612 3 104 27 2 725 1451 613 3 105 39 2 725 1451 614 3 107 264 2 725 1451 615 3 108 12 2 725 1451 616 3 600 250 2 725 1451 617 3 601 25 2 725 1451 618 3 602 21 2 725 1451 619 3 603 22 2 725 1451 620 3 604 18 2 725 1451 621 3 605 19 2 725 1451 622 3 606 19 2 725 1451 623 3 650 17 2 725 1451 624 3 651 19 2 725 1451 625 3 652 18 2 725 1451 626 3 653 15 2 725 1451 627 3 700 33 2 725 1451 628 3 701 16 2 725 1451 629 3 800 244 2 725 1451 630 3 801 92 2 725 1451 631 3 802 66 2 725 1451 632 3 803 41 2 725 1451 633 3 804 24 2 725 1451 634 3 805 23 2 725 1451 635 3 806 20 2 725 1451 636 3 807 20 2 725 1451 637 3 808 18 2 725 1451 638 3 809 18 2 725 1451 639 3 810 16 2 725 1451 640 4 2 1992 4 725 1451 641 4 51 86 2 725 1451 642 4 52 68 2 725 1451 643 4 53 74 2 725 1451 644 4 54 74 2 725 1451 645 4 55 70 2 725 1451 646 4 56 70 2 725 1451 647 4 57 36 2 725 1451 648 4 58 28 2 725 1451 649 4 59 16 2 725 1451 650 4 60 16 2 725 1451 651 4 61 18 2 725 1451 652 4 62 12 2 725 1451 653 4 63 2 1 725 1451 654 4 64 2 1 725 1451 655 4 65 2 1 725 1451 656 4 66 2 1 725 1451 657 4 67 2 1 725 1451 658 4 68 2 1 725 1451 659 4 69 2 1 725 1451 660 4 70 2 1 725 1451 661 4 71 2 1 725 1451 662 4 72 2 1 725 1451 663 4 73 2 1 725 1451 664 4 74 2 1 725 1451 665 4 75 2 1 725 1451 666 4 76 2 1 725 1451 667 4 77 2 1 725 1451 668 6 5 4575 4 725 1451 669 6 16 131 2 725 1451 670 12 102 217 5 725 1451 671 13 4 2127 2 725 1451 672 13 28 70 2 725 1451 673 13 32 6 2 725 1451 674 13 103 293 2 725 1451 675 13 104 128 2 725 1451 676 13 105 19 2 725 1451 677 13 107 1010 2 725 1451 678 14 4 66 2 725 1451 679 14 28 18 2 725 1451 680 14 32 1 1 725 1451 681 14 102 139 5 725 1451 682 14 103 1 1 725 1451 683 14 104 18 2 725 1451 684 14 105 1 1 725 1451 685 14 107 1 1 725 1451 686 15 102 210 1 725 1451 687 725 1 0 688 725 0 0 689 7.01400E+3 1.38827E+1 0 0 1 0 725 2151 690 7.014000+3 1.000000+0 0 0 1 0 725 2151 691 1.000000-5 1.000000+3 0 0 0 0 725 2151 692 1.000000+0 8.863659-1 0 0 0 0 725 2151 693 725 2 0 694 725 0 0 695 7.01400E+3 1.38827E+1 0 0 0 0 725 3 1 696 0.0 0.0 0 0 1 1622 725 3 1 697 1622 2 725 3 1 698 1.00000E-5 105.581400 1.09051E-5 101.525199 1.21607E-5 96.6667682 725 3 1 699 1.33221E-5 92.7989378 1.47465E-5 88.6941323 1.63750E-5 84.6740683 725 3 1 700 1.75872E-5 82.0515512 1.91611E-5 79.0252559 2.08855E-5 76.1106161 725 3 1 701 2.26528E-5 73.4758487 2.51417E-5 70.2475841 2.66442E-5 68.5216776 725 3 1 702 2.94929E-5 65.6192392 3.27499E-5 62.7766138 3.51745E-5 60.9220629 725 3 1 703 3.83221E-5 58.7822874 4.17709E-5 56.7213200 4.53055E-5 54.8582537 725 3 1 704 5.02833E-5 52.5755209 5.32883E-5 51.3551184 5.89856E-5 49.3028143 725 3 1 705 6.54997E-5 47.2927382 7.03489E-5 45.9813709 7.66442E-5 44.4682970 725 3 1 706 8.35419E-5 43.0240799 8.45897E-5 42.8057242 9.06110E-5 41.7055439 725 3 1 707 9.19727E-5 41.4580409 .000100000 40.1650563 .000100566 40.0843908 725 3 1 708 .000106576 39.2322460 .000109051 38.8829039 .000117971 37.7897068 725 3 1 709 .000121607 37.3467108 .000131000 36.3561181 .000133221 36.1230702 725 3 1 710 .000140698 35.4403858 .000147465 34.8253635 .000153288 34.3692251 725 3 1 711 .000163750 33.5539330 .000167084 33.3250198 .000175872 32.7246853 725 3 1 712 .000181222 32.3983168 .000191611 31.7680580 .000200000 31.3183943 725 3 1 713 .000201133 31.2576636 .000208855 30.8457468 .000213153 30.6425090 725 3 1 714 .000226528 30.0130750 .000235942 29.6254602 .000251417 28.9922253 725 3 1 715 .000261998 28.6069411 .000266442 28.4459575 .000281395 27.9632544 725 3 1 716 .000294929 27.5283640 .000306576 27.2057938 .000327499 26.6293160 725 3 1 717 .000334167 26.4674487 .000351745 26.0428968 .000362444 25.8121392 725 3 1 718 .000383221 25.3664971 .000402266 25.0055708 .000417709 24.7143177 725 3 1 719 .000426306 24.5705889 .000453055 24.1255244 .000471885 23.8514078 725 3 1 720 .000502833 23.4036682 .000523998 23.1311901 .000532883 23.0173950 725 3 1 721 .000562792 22.6760347 .000589856 22.3685632 .000613153 22.1404402 725 3 1 722 .000654997 21.7328244 .000668335 21.6183488 .000703489 21.3181599 725 3 1 723 .000724889 21.1549732 .000766442 20.8398620 .000804532 20.5869391 725 3 1 724 .000845897 20.3136060 .000852612 20.2746873 .000919727 19.8876004 725 3 1 725 .000943770 19.7646601 .001000000 19.4789250 .001047995 19.2631932 725 3 1 726 .001090508 19.0731010 .001125583 18.9368896 .001216071 18.5871619 725 3 1 727 .001226307 18.5529013 .001332208 18.2003396 .001336670 18.1874072 725 3 1 728 .001449778 17.8613202 .001474642 17.7900089 .001609065 17.4578316 725 3 1 729 .001637494 17.3879044 .001705226 17.2411566 .001758723 17.1257849 725 3 1 730 .001887541 16.8777523 .001916104 16.8230769 .002000000 16.6812248 725 3 1 731 .002088547 16.5315085 .002095992 16.5203464 .002251166 16.2889862 725 3 1 732 .002265277 16.2680395 .002452614 16.0248228 .002514163 15.9453043 725 3 1 733 .002664414 15.7726016 .002673341 15.7634539 .002899555 15.5328757 725 3 1 734 .002949282 15.4824517 .003218129 15.2475640 .003274986 15.1981185 725 3 1 735 .003410451 15.0943506 .003517447 15.0127683 .003775082 14.8373822 725 3 1 736 .003832209 14.7987199 .004177095 14.5925485 .004191983 14.5846567 725 3 1 737 .004502332 14.4210588 .004530554 14.4062472 .004905227 14.2342664 725 3 1 738 .005028326 14.1780376 .005328829 14.0559171 .005346681 14.0494494 725 3 1 739 .005799109 13.8864051 .005898565 13.8507489 .006436256 13.6846582 725 3 1 740 .006549972 13.6496941 .006820899 13.5763194 .007034893 13.5186311 725 3 1 741 .007550161 13.3946140 .007664418 13.3672748 .008354190 13.2214886 725 3 1 742 .008383964 13.2159086 .009004663 13.1002264 .009061108 13.0897528 725 3 1 743 .009810454 12.9681431 .010000000 12.9375321 .010056652 12.9283831 725 3 1 744 .010657657 12.8420308 .010693363 12.8374572 .011598218 12.7221673 725 3 1 745 .011797128 12.6969548 .012872514 12.5795102 .013099944 12.5547871 725 3 1 746 .013641800 12.5029031 .014069786 12.4621114 .015100323 12.3744180 725 3 1 747 .015328835 12.3550864 .016767928 12.2486336 .016943185 12.2357338 725 3 1 748 .018009326 12.1678226 .018729510 12.1221567 .019620909 12.0733475 725 3 1 749 .020000000 12.0527017 .020769123 12.0108140 .021591241 11.9713037 725 3 1 750 .022285693 11.9381011 .023372171 11.8916499 .024252456 11.8541469 725 3 1 751 .024316988 11.8516373 .025300000 11.8135000 .027589846 11.7328513 725 3 1 752 .029762844 11.6667050 .030766577 11.6363003 .032740711 11.5845343 725 3 1 753 .033704840 11.5593812 .035460884 11.5195136 .037308418 11.4777775 725 3 1 754 .038756968 11.4495728 .041428573 11.3978424 .042629201 11.3773603 725 3 1 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