A Nuclear Cross Section Data Handbook

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criticisms; the latter for his modification of the FICHE code which facilitated the for- matting of the text, for gathering and assimilating the necessary headiig information and for his special brand of fastidiousness and attention to detail whkh assured that the quality and completeness of the document would be maintained. Lastly, I thank Mrs. Helen Byers for the many hours we spent discussing ~ in general and its use and application to the Handbook in particular. . .. Vlll
A NUCLEAR CROSS SECTION DATA HANDBOOK by Harl’O M. Fisher ABSTRACT Isotopic information, reaction data, data availabilit y, heating numbers, and evaluation information are given for 129 neutron cross-section evaluations, which are the source of the default cross sections for the Monte Carlo code MCNP. Additionally, pie diagrams for each nuclide displaying the percent contribution of a given reaction to the the total cross section are given at 14 MeV, 1 MeV, and thermal energy. Other information about the evaluations and their availability in continuous-energy, discrete-reaction, and multigroup forms is provided. The evaluations come from ENDF/B-V, ENDL85, and the Los Alamos Applied Nuclear Science Group T-2. Graphs of all neutron and photon production cross-section reactions for these nuclides have been categorized and plotted. I. INTRODUCTION Cross-section data are the essential and absolutely necessary component of the input to all radiation transport codes; indeed, cross sections must exist for every element and isotope which appear in a transport problem in order to effect a solution of that problem. It is the cross sections which contain information about what happens to the neutrons and photons when they collide with atoms of the material through which they pass. Furthermore, the physics information distinguishing one element from another is also cent ained in the cross sections. Neutral-particle transport codes such as the Monte Carlo code MCNPl need neutron interaction, neutron-induced photon production, and photon interaction cross sect ions to perform the many and varied evaluat ions and calculations to which the ascribe. This Handbook provides information about the neutron interaction and photon production cross sections for the evaluations on which default cross sections for MCNP are based, These “neutron” cross sections are compiete in the sense that cross sections, angular distributions, and secondary energy distributions for each reaction are available; cross sections for producing photons along with the energy 1
Page 1 and 2: LA-11711-M Manual .;,, C3* ;’ !::
Page 3: A Nuclear Cross Section Data Handbo
Page 6 and 7: Li-6 . . . . . . . . . Li-7 . . . B
Page 8 and 9: Ag-107 . . . . . . . . . . . . . .
Page 10 and 11: Np-237 Np-238 Pu-237 Pu-238 Pu-239
Page 14 and 15: and angular distributions of the in
Page 16 and 17: value used in calculating the mean
Page 18 and 19: A. Tabular Data There are 129 sets
Page 20 and 21: ~Uij(E) j The “total” heating n
Page 22 and 23: the future generation of this docum
Page 24 and 25: 11. R. J. Howerton, R. E. Dye,P. C.
Page 26 and 27: Actinium Aluminum Americium Antimon
Page 28 and 29: MT 1 2 4 16 17 18 19 20 21 22 24 25
Page 30 and 31: Reaction elaat ic (n,-f) Hydrogen-1
Page 32 and 33: Reaction elastic (n,2n) (n,2n) (n,.
Page 34 and 35: TYitium - 3 ZAID=1OO3.5OC SOURCE: E
Page 36 and 37: Re~tion eleetk (n,p) (n,d) Helium -
Page 38 and 39: Helium - 4 ZAID=2004.50C SOURCE: EN
Page 40 and 41: Reaction MT elaatic 2 (n,%l)u (n,n
Page 42 and 43: Reaction elaatk (n#n) (m,2m)a (m,h)
Page 44 and 45: Beryllium - 7 ZAID=4007.35C SOURCE:
Page 46 and 47: Beryllium - 9 ZAID=4009.50C SOURCE:
Page 48 and 49: Boron - 10 ZAID=501O.5OC SOURCE: EN
Page 50 and 51: REFERENCE: Boron - 11 ZAID=5011.56C
Page 52 and 53: Reaction elaatk (n#l’l) (Il,n’)
Page 54 and 55: Reaction elastic (n#’l) (SI,sl’
Page 56 and 57: REFERENCE: elaatk (n#’l) (n,m’a
Page 58 and 59: Reection eleet ic (n,2n) (n,n’1)
Page 60 and 61: Reaction elastic (n,2n) (n,n’)u (
Page 62 and 63:
Reaction elaat ic (n,n’1) (n,n’
Page 64 and 65:
SOURCE:ENDF/B-V(MAT=1309, Reaction
Page 66 and 67:
Reaction elantic (n,2n) (n,n’1) (
Page 68 and 69:
Reaetion elaatic (n,2n) (n,n’)a (
Page 70 and 71:
Reaction elastic (n,2n) (n,n’1) (
Page 72 and 73:
Silicon ZAID=14000050C SOURCE:ENDF/
Page 74 and 75:
Ruaction alast k (rl,an) (Il,n’)p
Page 76 and 77:
Reaction elastic (n,2n) (n,n’)p (
Page 78 and 79:
Reaction elastic (n,2n) (n,n’)ff
Page 80 and 81:
Argon ZAID=18000.35C SOURCE: ENDL-8
Page 82 and 83:
Reaction elastic (n,2n) (n,n’)a [
Page 84 and 85:
Reection elaotk (n#m) (Il,n’)a (n
Page 86 and 87:
Reaction elaetic (n,2n) (n,Sn) (n,n
Page 88 and 89:
Vanadium ZAID=23000.50C SOURCE:ENDF
Page 90 and 91:
Reaction elaet ic (n,2n) (n,$n) (n,
Page 92 and 93:
Reaction elwkic (n,an) (n,$n) (n,n
Page 94 and 95:
Reaction elastic (n,2n) (n,n’)o (
Page 96 and 97:
Reaction elastic (n,2n) (n,n’)a (
Page 98 and 99:
Reaction elastic (n,an) (n,n’)a (
Page 100 and 101:
Nickel - 58 ZAID=28058.35C SOURCE:
Page 102 and 103:
Reaction eleatk (SI,an) (Sl,sn) (n,
Page 104 and 105:
Gallium ZAID=31OOO.5OC SOURCE:ENDF/
Page 106 and 107:
Arsenic - 74 ZAID=33074.35C ~ SOURC
Page 108 and 109:
Arsenic - 75 ZAID=33075.35C SOURCE:
Page 110 and 111:
Reaction elaat ic (n,2n) (n,n’1)
Page 112 and 113:
Reaction elastic (n,2n) (n,n’1) (
Page 114 and 115:
Reaction ela8tic (n,2n) (n,n’1) (
Page 116 and 117:
Reaction elaatk (m*) (I@l) (81,BI
Page 118 and 119:
Reaction elaetic (n,2n) (m,n’1) (
Page 120 and 121:
Reaction elastk (I@n) (n,wl) (n,n
Page 122 and 123:
REFERENCE: Reaction elaatk (n,n’c
Page 124 and 125:
Yttrium - 89 ZAID=39089.50C SOURCE:
Page 126 and 127:
● Reaction elastic (n,2n) (n,n’
Page 128 and 129:
Reaction eleatic (n,2n) (n,3n) g,:;
Page 130 and 131:
Molybdenum ZAID=42000.50C SOURCE: E
Page 132 and 133:
Rhodium - 103 ZAID=45103.5OC SOURCE
Page 134 and 135:
●la9tk (Il,2n) (18,h) (n,n’c) (
Page 136 and 137:
Average Fission Product from 23’P
Page 138 and 139:
Reaction eleet k (n,2n) (n,n’1) (
Page 140 and 141:
Silver - 107 ZAID=47107.5OC SOURCE:
Page 142 and 143:
Silver - 109 ZAID=47109.5OC SOURCE:
Page 144 and 145:
Reaction ela8tic (n,2n) (n,rl’1)
Page 146 and 147:
Tin ZAID=50000.35C SOURCE:ENDL-85(Z
Page 148 and 149:
REF Reaction elaatk (n#l’c) (Il,2
Page 150 and 151:
Xenon ZAID=54000.35C SOURCE:ENDL-85
Page 152 and 153:
Xenon - 134 ZAID=54134.35C SOURCE:E
Page 154 and 155:
Reaction elastic (n,an) (n,ml) (n,n
Page 156 and 157:
Samarium - 149 ZAID=62149.50C SOURC
Page 158 and 159:
Europium ZAID=63000.35C SOURCE: END
Page 160 and 161:
Reaction elaatic (n,2n) (n,3n) (n,n
Page 162 and 163:
Reaction elastic (n,2n) (n,3n) (n,n
Page 164 and 165:
Reaction (n,an) (n,h) (n,n’1) (11
Page 166 and 167:
R.caetion elaatk (n,all) (n,srl) (n
Page 168 and 169:
Gadolinium ZAID=64000.35C SOURCE: E
Page 170 and 171:
&action llastic ~n,!ht) Il,n’)u :
Page 172 and 173:
Reaction elastic (n,2n) (n,n’)cr
Page 174 and 175:
Reaction elastic (n,2n) (n,n’)a (
Page 176 and 177:
Reaction elaet ic (n,2n) (n,n’)a
Page 178 and 179:
Reaction elaatic (n,2n) (n,n’)u (
Page 180 and 181:
Reaction elastk (n,am) (a,m’)o (n
Page 182 and 183:
Gadolinium - 160 ZAID=64160.50C SOU
Page 184 and 185:
elaetk (n,2n) (I@l) (n,4n) (n,n’1
Page 186 and 187:
Reaction ela8tic (n,2n) (n,n’1) (
Page 188 and 189:
Reaction elastic (n,~n) (n,3n) (n,n
Page 190 and 191:
Reaction elastic (n,2n) (n,3n) (n,n
Page 192 and 193:
Reaction eleetic (n,2n) (n,h) @d$ (
Page 194 and 195:
Reaetion elastic (n,!h) (n,3n) [:::
Page 196 and 197:
Reaction ellwtic (n,an) 1; (m,%) (m
Page 198 and 199:
Page 200 and 201:
OIMtic (n*am) (Ib,h) (n,m’1) (n,n
Page 202 and 203:
Reaction eleetic (n,2n) (n,.$u) (n,
Page 204 and 205:
Platinum ZAID=78000.35C SOURCE: END
Page 206 and 207:
Reaction elastic (n,2n) (n,3n) (n,4
Page 208 and 209:
Page 210 and 211:
Reaetion 91a8tic (n,an) (n,sn) (n,n
Page 212 and 213:
Thorium - 231 ZAID=90231.35C SOURCE
Page 214 and 215:
Thorium - 232 ZAID=90232.50C . SOUR
Page 216 and 217:
Thorium - 233 ZAID=90233.35C SOURCE
Page 218 and 219:
Reaction elastic (n,2n) (n,Sn) flui
Page 220 and 221:
Uranium - 233 ZAID=92233,50C‘ SOU
Page 222 and 223:
Uranium - 234 ZAID=92234.50C SOURCE
Page 224 and 225:
Reaction elaetic (n,2n) (n,Sn) (n,f
Page 226 and 227:
Reaction elastic (n,2n) (n,3n) (n,f
Page 228 and 229:
Page 230 and 231:
Reaction elastic (n,2n) ~n#l) (n,n
Page 232 and 233:
Uranium - 239 ZAID=92239.35C~ SOURC
Page 234 and 235:
Page 236 and 237:
● Neptunium - 235 ZAID=93235.35C
Page 238 and 239:
Neptunium - 236 ZAID=93236.35C , SO
Page 240 and 241:
Reaction elastic (n,2n) (n,3n) fiss
Page 242 and 243:
Neptunium - 238 ZAID=93238.35C SOUR
Page 244 and 245:
Plutonium - 237 ZAID=94237.35C SOUR
Page 246 and 247:
Page 248 and 249:
Reaction eleetic (n,2n) (n,Sn) fiss
Page 250 and 251:
Reaction elestic (n,2n) (n,Sn) (n,f
Page 252 and 253:
Reaction elaatic (n,2n) (n,Sn) fiss
Page 254 and 255:
Reaction elastic (n,2n) (n,3n) fiss
Page 256 and 257:
Plutonium - 243 ZAID=94243.35C SOUR
Page 258 and 259:
Page 260 and 261:
Reaction elestic (n,ln) (n,3n) (n,f
Page 262 and 263:
Reaction elaatic (n,2n) [:::;) (n,n
Page 264 and 265:
elastic (n,2n) [;::;) (n,n’f) (n,
Page 266 and 267:
Curium - 243 ZAID=96243.35C SOURCE:
Page 268 and 269:
Curium - 244 ZAID=96244.50C~ SOURCE
Page 270 and 271:
Page 272 and 273:
Page 274 and 275:
Page 276 and 277:
Page 278 and 279:
REFERENCE: Reaction elaatlc (n#l’
Page 280 and 281:
Californium - 249 ZAID=98249.35C SO
Page 282 and 283:
Page 284 and 285:
Page 286 and 287:
Page 288 and 289:
Density Values APPENDIX A EXPLANATO
Page 291 and 292:
001425 Ao2 02tw350 A03 0s1475 A04 0
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A Nuclear Cross Section Data Handbook

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