A Nuclear Cross Section Data Handbook

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Reaction elastic (n,2n) (n,n’)o (n,n’)p (n,n’1) (n,n’2) (n,n’3) (n,n’4) (n,n’5) (n,n’6) (n,n’7) (n,n’8) (n,n’9) (n,n’10) (n,n’11) (n,n’12) (n,n’13) (n,n’14) (n,n’15) (n,n’16) (n,n’17) (n,n’18) (n,n’19) (n,tl’20) (n,n’21) (n,n’22) (n,n’23) (n,n’24) (n,n’25) (n,n’26) (n,n’27) (n,n’2.s) (n,n’29) (n,n’30) (n,n’31) (n,n’32) (n,n’33) (n,n’34) (n,n’35) (n,n’36) (n,u’37) (n,n’38) (n,n’39) f:::;:;) (n,-j) (n$p) (n,d) (n$t) [~;~Ie) iron ZAID=26000.55C SOURCE: Group T-2 (MAT=26o, File /T2/PGY/FE5/LAFE) REFERENCE: “Evaluated Neutron-Induced Cross Sections for 54,56Fe to 40 MeV ,“ by E, D. Arthur and P. G. Young Los Alamos National Laboratory report LA-8826-MS (December 1980) pat. A vailability Continuous Energy ZAID=26000.55C NES=6S99 T=300”K Discrete Reaction ZAID=26000,55D NES=263 T=300”K Multigroup ZAID=26000,55M 30-Group T=300”K JsotoDe [nformation Abundance= Natural Density =7.86 gm/cm3 Evaluation Information Photon-Production Data – Yes Heating Numbers – Local Energy Range – 10-11 to 20 MeV h~n ati MT Emin (MeV) E=.. (MeVl Ov(MeVl 2 i .0000 -11 2“XOOO+0’I ‘“. ‘ ‘ 16 i. 1399+01 2.0000+01 -1.1197+01 QR(MeV) -1.1197+01 22 28 51 52 H 55 56 57 58 59 :: 62 63 64 65 % 7.7515+00 9. oi30+oo 8.6210-01 1. 4342+00 2. 1228+00 2. 5944+00 2. 6076+00 2.7056+00 3. 0000+00 3. 0135+00 3. 0135+00 3. 1764+00 3. 1794+00 3. 2233+00 3. 3547+00 3. 4054+00 3.4311+00 3. 4492+00 3. 5072+00 2.0000+01 2. 0000+01 2. 0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.000o+oi -7.6140+00 -8:8530+00 -8.4680-01 -1,4084+00 -2.0851+00 -2.5384+00 -2.6613+00 -2.6576+00 -2.9417+00 -2.9590+00 -2.9600+00 -3.1200+00 -3.1230+00 -3.1661+00 -3.2952+00 -3.3450+00 -3.3702+00 -3.3880+00 -3.4450+00 -7.6140+00 -8.8530+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 68 69 70 3.5123+00 3.6670+00 3.6729+00 2.0000+01 2.0000+01 ---- 2.0000+Oj -3.4500+00 -3.6019+00 ------ -3.6070+00 -- 0.0000+00 0.0000+00 0.0000+00 71 3.8300+00 2.0000+01-3.7558+00 0.0000+00 72 3.9012+00 2.0000+01-3.8320+00 0.0000+00 73 74 75 76 77 78 79 80 81 82 3.9262+00 4.1221+00 4.1744+00 4.1944+00 4.3756+00 4.3797+00 4.4744+00 4.4805+00 4.5385+00 4.5915+00 2.0000+01 -3.8565+00 2.0000+01-4.0490+00 2.0000+01 . . . -4.iooi+oo ---- 2.0000+01-4:1200+00 2.0000+01 -4.2980+00 2.0000+01-4.3020+00 2.0000+01-4.3950+00 2.0000+01 -4.4010+00 2.0000+01 -4.4580+00 2.0000+01 -4.s100+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 0.0000+00 83 84 4.6215+00 4.6363+00 2.0000+01 2.0000+01 -4.5395+00 -4.5540+00 0.0000+00 0.0000+00 :! 4.6953+00 4.7442+00 2.0000+01 2.0000+01 -4.6120+00 -4.6600+00 0.0000+00 0.0000+00 4.7693+00 2.0000+01 -4.6847+00 0.0000+00 88 89 90 4.8153+00 4.8252+00 4.9661+00 2.0000+01 2.0000+01 2.0000+01 -4.7299+00 -4.7396+00 -4.8780+00 0.0000+00 0.0000+00 0.0000+00 1:: 103 104 105 106 4.9661+00 1.0000-11 1.0000-11 8.1028+00 1.2144+01 1.0723+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 2.0000+01 -4.8780+00 7.7500+00 8.5300-02 -7.9590+00 -1.1928+01 -1.0533+01 -4.8780+00 7.7500+00 8.5300-02 -7.9590+00 -1.1928+01 -1.0533+01 i07 1.0000-11 2.0000+01 3.2610-01 3.2610-01 82 THERMAL smwl’ - 14.(W fw’m UFP= 0E4 m E=tOOMP SICIVT .6.1.9bamu MFP= 227 mn E=t4.00IW’ SICIOT = 2s8 btuna l(l?P=456cnl
SJ ~ \. \ \, \\ \, \ \ J[ # ‘“’w ‘“--d t “’”’-d “’%-J ““’-d ““’”’d “’””” lrf‘ ““””””~ td hduncn!rw(dv) ‘ )~..7v, j~ I ...w. --,-- .,.:.- --~ ‘NmAL&m(A” ‘a I 26000.55C - W.mooodsc ● -MT o’mmRnms W.1 w! m-a mbmc —— .—— Ur-im MwRRmN lAID-s6000M b-w hmRMcc9 UT-w XMUAPmDtmmN rAxD-s60mmc h-NAr $bn NMcxs —.—.— .— l%j’m .................. R&s m’-mr NAUYIA 83 / WAvav XAID- f6000SW n-nm nwmNmccs MT-4 lV7AL!NE-Ic %&Y —.—.—.— KE%PN4 .................. iwfl MT-m DEUTCRNM PNaD — .—. —._ Mr-206 TNJr[urnPROD kr-m NE-.7PROD MT-m ALPHAPROD
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LA-11711-M Manual .;,, C3* ;’ !::
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A Nuclear Cross Section Data Handbo
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Li-6 . . . . . . . . . Li-7 . . . B
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Ag-107 . . . . . . . . . . . . . .
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Np-237 Np-238 Pu-237 Pu-238 Pu-239
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criticisms; the latter for his modi
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and angular distributions of the in
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value used in calculating the mean
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A. Tabular Data There are 129 sets
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~Uij(E) j The “total” heating n
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the future generation of this docum
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11. R. J. Howerton, R. E. Dye,P. C.
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Actinium Aluminum Americium Antimon
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MT 1 2 4 16 17 18 19 20 21 22 24 25
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Reaction elaat ic (n,-f) Hydrogen-1
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Reaction elastic (n,2n) (n,2n) (n,.
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TYitium - 3 ZAID=1OO3.5OC SOURCE: E
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Re~tion eleetk (n,p) (n,d) Helium -
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Helium - 4 ZAID=2004.50C SOURCE: EN
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Reaction MT elaatic 2 (n,%l)u (n,n
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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 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:
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Reaction ela8tic (n,2n) (n,rl’1)
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Tin ZAID=50000.35C SOURCE:ENDL-85(Z
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REF Reaction elaatk (n#l’c) (Il,2
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Xenon ZAID=54000.35C SOURCE:ENDL-85
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Xenon - 134 ZAID=54134.35C SOURCE:E
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Reaction elastic (n,an) (n,ml) (n,n
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Samarium - 149 ZAID=62149.50C SOURC
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Europium ZAID=63000.35C SOURCE: END
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Reaction elaatic (n,2n) (n,3n) (n,n
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Reaction elastic (n,2n) (n,3n) (n,n
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Reaction (n,an) (n,h) (n,n’1) (11
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R.caetion elaatk (n,all) (n,srl) (n
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Gadolinium ZAID=64000.35C SOURCE: E
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&action llastic ~n,!ht) Il,n’)u :
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Reaction elastic (n,2n) (n,n’)cr
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Reaction elastic (n,2n) (n,n’)a (
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Reaction elaet ic (n,2n) (n,n’)a
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Reaction elaatic (n,2n) (n,n’)u (
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Reaction elastk (n,am) (a,m’)o (n
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Gadolinium - 160 ZAID=64160.50C SOU
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elaetk (n,2n) (I@l) (n,4n) (n,n’1
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Reaction ela8tic (n,2n) (n,n’1) (
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Reaction elastic (n,~n) (n,3n) (n,n
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Reaction elastic (n,2n) (n,3n) (n,n
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Reaction eleetic (n,2n) (n,h) @d$ (
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Reaetion elastic (n,!h) (n,3n) [:::
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Reaction ellwtic (n,an) 1; (m,%) (m
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OIMtic (n*am) (Ib,h) (n,m’1) (n,n
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Reaction eleetic (n,2n) (n,.$u) (n,
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Platinum ZAID=78000.35C SOURCE: END
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Reaction elastic (n,2n) (n,3n) (n,4
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Reaetion 91a8tic (n,an) (n,sn) (n,n
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Thorium - 231 ZAID=90231.35C SOURCE
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Thorium - 232 ZAID=90232.50C . SOUR
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Thorium - 233 ZAID=90233.35C SOURCE
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Reaction elastic (n,2n) (n,Sn) flui
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Uranium - 233 ZAID=92233,50C‘ SOU
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Uranium - 234 ZAID=92234.50C SOURCE
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Reaction elaetic (n,2n) (n,Sn) (n,f
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Reaction elastic (n,2n) (n,3n) (n,f
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Reaction elastic (n,2n) ~n#l) (n,n
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Uranium - 239 ZAID=92239.35C~ SOURC
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● Neptunium - 235 ZAID=93235.35C
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Neptunium - 236 ZAID=93236.35C , SO
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Reaction elastic (n,2n) (n,3n) fiss
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Neptunium - 238 ZAID=93238.35C SOUR
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Plutonium - 237 ZAID=94237.35C SOUR
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Page 248 and 249:
Reaction eleetic (n,2n) (n,Sn) fiss
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Reaction elestic (n,2n) (n,Sn) (n,f
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Reaction elaatic (n,2n) (n,Sn) fiss
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Reaction elastic (n,2n) (n,3n) fiss
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Plutonium - 243 ZAID=94243.35C SOUR
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Page 260 and 261:
Reaction elestic (n,ln) (n,3n) (n,f
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Reaction elaatic (n,2n) [:::;) (n,n
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elastic (n,2n) [;::;) (n,n’f) (n,
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Curium - 243 ZAID=96243.35C SOURCE:
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Curium - 244 ZAID=96244.50C~ SOURCE
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Page 272 and 273:
Page 274 and 275:
Page 276 and 277:
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REFERENCE: Reaction elaatlc (n#l’
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Californium - 249 ZAID=98249.35C SO
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Page 284 and 285:
Page 286 and 287:
Page 288 and 289:
Density Values APPENDIX A EXPLANATO
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001425 Ao2 02tw350 A03 0s1475 A04 0
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A Nuclear Cross Section Data Handbook

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