International Reactor Dosimetry File 2002 - IAEA Publications

TABLE 2.2. MEASURED AND CALCULATED AVERAGED CROSS-
SECTIONS IN THE URANIUM-235 THERMAL FISSION NEUTRON
SPECTRUM
Reaction
Updated RRDF-98
(mb)
IRDF-90
(mb)
Experimental (mb)
19 F(n,2n) 18 F 0.007299 0.00772 0.007200 ± 0.00100 [2.18]
0.008624 ± 0.00046 [2.31]
24 Mg(n,p) 24 Na 1.5396 1.5517 1.455 ± 0.023 [2.30]
1.451 ± 0.023 [2.31]
27 Al(n,p) 27 Mg 4.0768 — 4.133 ± 0.074 [2.28]
3.914 ± 0.070 [2.30]
3.902 ± 0.069 [2.31]
46 Ti(n,2n) 45 Ti 0.004469 — —
46 Ti(n,p) 46 Sc m+g 11.447 10.252 11.51 ± 0.20 [2.31]
47 Ti(n,x) 46 Sc m+g 0.008116 — —
48 Ti(n,p) 48 Sc 0.3043 0.2749 0.305 ± 0.020 [2.28]
0.2996 ± 0.0054 [2.31]
48 Ti(n,x) 47 Sc 0.001656 — —
49 Ti(n,x) 48 Sc 0.001004 — —
51 V(n,α) 48 Sc 0.02441 0.0246 0.02429 ± 0.00056 [2.31]
54 Fe(n,2n) 53 Fe m+g 0.001284 — —
54 Fe(n,α) 51 Cr 0.8459 — 0.850 ± 0.050 a
56 Fe(n,p) 56 Mn 1.1085 1.0297 1.130 ± 0.070 [2.28]
1.083 ± 0.017 [2.30]
1.079 ± 0.017 [2.31]
59 Co(n,α) 56 Mn 0.1582 0.1549 0.1563 ± 0.0035 [2.31]
58 Ni(n,p) 58 Co 107.44 105.73 108.2 ± 1.4 [2.31]
63 Cu(n,α) 60 Co m+g 0.5329 0.5214 0.5295 ± 0.0255 [2.29]
0.4918 ± 0.0242 [2.31]
75 As(n,2n) 74 As 0.3092 — 0.309 ± 0.019 a
93 Nb(n,2n) 92 Nb m 0.4416 0.4459 0.4576 ± 0.0226 a
0.4645 ± 0.0117 [2.31]
93 Nb(n,n′) 93 Nb m 143.46 139.97 147.6 ± 7.0 a
103 Rh(n,n′) 103 Rh m 715.85 706.03 702.2 ± 28.1 [2.26]
721.2 ± 38.7 [2.28]
115 In(n,n′) 115 In m 188.40 186.35 188.2 ± 2.3 [2.30]
187.8 ± 2.3 [2.31]
10