Effective Cross Sections for Fission-Spectrum Neutrons 
Reaction Half-life Er(Mev) o.(mb) Re. Reaction Half-life E7r(Mev) o.(mb) Ref. 
Al?7(n,p)Mg?? 10.2m 1.90 3.43 12 Ni®*(n,p)Cos* 72d —0.64 40. 16 
2.8 13 45. 17 
Al??(n,a)Na% 15h 3.27. 0.60 12 45. 18 
0.6 13 140. 8 
0.44 7 225, 14 
Ba!®2(n,p)Cg!32 6.2d ~0. 5.3 14 Ni®8(n,p)Co88™ 9.0h —0.64 13. 6 
Ba!36(n,p)Cs136 13d 2.06 0.0015 14 Ni®8(n,a) Fes 2.9y —3.06 0.17 16 
Be®(n,«) He® 0.823 Owl ~—«i10. 13 Ni®8(n,2n) Nis? 36h 12.0 0.0012 16 
B!!(n,a)Li8 0.8438 7.24 0.085 13 Ni®°(n,p)Co® 5. 4y 2.07 <4.5 14 
Cd119(n,p) Agi? 270d 2.12 ~0.1 8 5. 6 
Cl35(n,p)S3* 87d =0.62-— 16: 13 <2. 8 
C135(n,a) P32 14.3d —0.92 3. 13 0.56 15 
4.1 tf Ni®?(n,a)Fe5® 45d 0.884 0.013 16 
Cl37(n,p)S3? 5.0m 3.6 0.24 13 0.025 6 
Co**(n,p) Fe5® 45d 0.79 0.25 16 0.14 8 
~0.3 8 O18(n,p) N16 7.53 10.22 0.014 13 
5.7 6 0.019 19 
Co*®(n,a) Mn* 2.58h —0.44 0.14 th 0.0185 20 
Cs!83(n, a) 113° 12.6h —4.22 2.4X10°* 7 O!(n,p)N"" 4.148 8.47 0.0052 19 
5. 10-4 6 0.0093 20 
Cu®(n,a)Co® 5.4y —1.59 0.72 8 P3!(n,p)Si34 170m 0.72 31.2 12 
F}9(n,p)O' 30s 4.21 0.5 13 19. 13 
0.99 7 P3!(n,ax) Al*8 2.4m 2.02 1.43 13 
F!9(n,a)N16 7.53 1.57 4.5 18 . 0.75 7 
4.5 7 S22(n,p) P32 14.3d 0.95 154. 16 
Fe*(n,p)Mn*4 291d —0.16 11. 16 60.3 12 
15. 16 30. 13 
23. 6 21. Uf 
56. 8 S34(n,a)Si3! 170m 1.24 3.0 13 
Fe®4(n,a)Cr®! 27.8d —0.862 0.37 6 1.2 if 
Fe®*(n,p)Mn** 2.58h 2.94 0.44 6 Sc48(n,a)K* 12.5h 0.61 <5. 8 
Ge7°(n,2n)Ge® 39.6h 11.9 1.5 8 Si?8(n,p) Al?8 2.4m 4.01 4. 138 
Ge??(n,p)Ga7? 14.1h 3.27 <0.01 8 Si?9(n,p) Al?® 6.7m 3.1 2.7 13 
Ge??(n,a)Zn® 13.8h —-1.12 <1. 8 Ta!®!(n,a)Lu!78 22m ? 8.5xX105 7 
Mg*4(n,p)Na* 15h 4.95 1.29 12 Th?3?(n,2n)Th*3! 25.6h 6.3 12.4 21 
1.0 13 Tit*(n,p)Se*® 85d 1.61 4.10 6 
Mg?5(n,p)Na* 628 3.1 2.0 13 Ti‘? (n,p)Se*7 3.4d —0.096 0.21 6 
Mn'*(n,2n)Mn* 291d =:10.38 0.05 (?) 16 BAUS DBs 44h $.28 0.077 “ 
j48 46 
Mo"(n,p)Nb" fa Sh deers a Ti**(n,a)Ca 164d 2.02 0.0055 6 
Ti5°(n,a)Ca‘? 4.74 3.58 0.0002 6 
Mo®?(n,a) Zr®* 79h —3.00 0.017 6 T1299(n,p) Hg? 48d 0.297 0.002 6 
‘; A 
Mo*5(n,p) Nb** 35d 0.150 <0.1 6 U298(n,2n)U237 6.6d 6.09 4.7 165 
Na**(n,p)Ne* 40s 3.76 0.7 18 V#1(n,a)Se4® 44h 2.14 0.08 13 
1.0 7 0.0099 7 
Na?3(n,2n)Na?? 2.6y 12.98 0.006 13 Zn"4(n,p)Cu -12.8h —0.22 35. 8 
Na®*(n,a)F? 11.68 4.07 0.4 18 22. 6 
0.47 if Zn®7(n,p)Cus? 59h —0.214 0.27 6 
Nb*3(n,a) Y*° 64.0h —4.87 0.024 a Zn®8(n,a) Ni® 2.56h —0.93 0.020 7 
bridge, Mass., 1953) A = 40 to A = 92,"" TID-5300 (1955) 16. G. H. Stafford, L. H. Stein, Nature 172, 1103 
4. A. H. Wapstra, Isotopic masses <202, 10. J. M. Hollander, et al. ‘‘Table of Isotopes,"’ (1953); basis for flux measurement not 
Physica 21, 367 (1955); and J. R. Huizenga, Rev. Mod. Phys. 26, 469 (1953) specified 
Isotopic masses >201, Physica 21, 410 (1955) 11. ‘‘Nuclear Data,'’ published monthly (Na- 17. C. E. Mellish, J. A. Payne, Nature 178, 275 
6. W. Inthoff, NucLEontcs 18, No. 11, 67 (1955) tional Research Council, Washington 25, (1956); based on assumed os = 30 mb for 
6. C. E. Mellish, J. A. Payne, R. L. Otlet in D.C.) S$32(n,p) P32 
‘Proc. International Conference on Radio- 12. R. Richmond, Atomic Energy Research 18. This value, taken from ref. 6, is sum of 
isotopes in Scientific Research,’’ Sept., 1957, Establishment, Harwell, England, private oe = 32 mb for direct production of 72-day 
Paris (Pergamon Press, London, 1958); communication (1957); based on assumed Co*8 and 13 mb for production of 9-hr Co5&™ 
based on assumed oe = 30 mb for S32(n,p) P32 U238 fission cross section of 304 mb which decays to Co8 
7. E. Saeland, K. Samsahl, Joint Establishment 13. Ref. 3, pp. 100 and 102; based on calculating 19. P. A. Roys, K. Shure, Nuclear Si. and Eng 
for Nuclear Energy Research, Lillestrom, flux near U slab in thermal-neutron beam 4, 536 (1958); based on assumed oe = 0.60 
Norway, JENER Report No. 23 and private 14. B. L. Robinson, R. W. Fink, University of mb for Al??(n,a)Na%4 
communication; based on assumed a» = 19 Arkansas, private communication; based on 20. W. J. Henderson, P. R. Tunnicliffe, Nuclear 
mb for P®!(n,p)Si#! assumed oe = 30 mb for S32(n,p) P32 Sci. and Eng. 3, 145 (1958); flux calculated 
8. Values measured by present author and not 16. R. P. Schuman, A. C. Mewherter, KAPL-1779 from reactor power level 
previously published; based on assumed (1957); based on assumption that fission- 21. J. A. Phillips, AERE-R/R-2366 (1957); 
ae = 0.60 mb for Al??(n,a) Na%4 neutron flux inside uranium receptacle slug based on assumed os = 60.3 mb for S2(n,p) P3? 
9. K. Way, et al. ‘‘Nuclear Level Schemes, equals thermal-neutron flux outside slug 22. 8. E. Turner, Anal. Chem. 28, 1457 (1956) 
247 
