3. DESCRIPTION
JENDL Dosimetry File 99 processed into ACE for Monte Carlo calculations.
JENDL/D-99 based MCNP library.
FORMAT: ACE
NUMBER OF GROUPS: Continuous energy cross section library.
Nuclides: 47 nuclides and 67 reactions:
Li-6 (n, triton) alpha ; Li-6 alpha-production ; Li-7 triton- production ; B-10 (n, alpha) Li-7 ; B-10 alpha-production ; F-19 (n, 2n) F-18 ; Na-23 (n, 2n) Na-22 ; Na-23 (n, gamma) Na-24 ; Mg-24 (n, p) Na-24 ; Al-27 (n, p) Mg-27 ; Al-27 (n, alpha) Na-24 ; P-31 (n, p) Si-31 ; S-32 (n, p) P-32 ; Sc-45 (n, gamma) Sc-46 ; Ti-nat (n, x) Sc-46 ; Ti-nat (n, x) Sc-47 ; Ti-nat (n, x) Sc-48 ; Ti-46 (n, 2n) Ti-45 ; Ti-46 (n, p) Sc-46 ; Ti-47 (n, np) Sc-46 ; Ti-47 (n, p) Sc-47 ; Ti-48 (n, np) Sc-47 ; Ti-48 (n, p) Sc-48 ; Ti-49 (n, np) Sc-48 ; Cr-50 (n, gamma) Cr-51 ; Cr-52 (n, 2n) Cr-51 ; Mn-55 (n, 2n) Mn-54 ; Mn-55 (n, gamma) Mn-56 ; Fe-54 (n, p) Mn-54 ; Fe-56 (n, p) Mn-56 ; Fe-57 (n, np) Mn-56 ; Fe-58 (n, gamma) Fe-59 ; Co-59 (n, 2n) Co-58 ; Co-59 (n, gamma) Co-60 ; Co-59 (n, alpha) Mn-56 ; Ni-58 (n, 2n) Ni-57 ; Ni-58 (n, p) Co-58 ; Ni-60 (n, p) Co-60 ; Cu-63 (n, 2n) Cu-62; Cu-63 (n, gamma) Cu-64; Cu-63 (n, alpha) Co-60 ; Cu-65 (n, 2n) Cu-64 ; Zn-64 (n, p) Cu-64 ; Y-89 (n, 2n) Y-88 ; Zr-90 (n, 2n) Zr-89 ; Nb-93 (n, n') Nb-93m ; Nb-93 (n, 2n) Nb-92m ; Rh-103 (n, n') Rh-103m ; Ag-109 (n, gamma) Ag-110m ; In-115 (n, n') In-115m ; In-115 (n, gamma) In-116m ; I-127 (n,2n) I-126 ; Eu-151 (n, gamma) Eu-152 ; Tm-169 (n,2n) Tm-168 ; Ta-181 (n, gamma) Ta-182 ; W-186 (n, gamma) W-187 ; Au-197 (n, 2n) Au-196 ; Au-197 (n, gamma) Au-198 ; Hg-199 (n, n') Hg-199m ; Th-232 - fission ; Th-232 (n, gamma) Th-233 ; U-235 - fission ; U-238 - fission ; U-238 (n, gamma) U-239 ; Np-237 - fission ; Pu-239 - fission ; Am-241 - fission
The data were produced on the 31st of March, 2006.
