Neutron Capture Cross Section of²⁴³Am

Review and Assessment of Neutron Cross Section and Nubar Covariances for Advanced Reactor Systems

“…4.4). 244 Cm(n,n') are too optimistic (low) (note the discrepancies of JENDL-3.3 (adopted for ENDF/B-VII.0) evaluated fission cross section with measured fission data by Fomushkin et al [115,116]. We consider these data most reliable.…”

“…16 237 Np(n, el) 2.17 241 Am(n, el) 2.18 243 Am(n, el) 2.19 242m Am(n, el) Chapter 3: Fission Cross Sections 3.1 232 Th(n, f) 3.2 238 U(n, f) 3.3 236 U(n, f) 3. 4 234 U(n, f) 3.5 238 Pu(n, f) 3.6 240 Pu(n, f) 3.7 242 Pu(n, f) 3.8 242 Cm(n, f) 3.9 244 Cm(n, f) 3.10 235 U(n, f) 3.11 233 U(n, f) 3.12 239 Pu(n, f) 3.13 241 Pu(n, f) 3.14 243 Cm(n, f) 3.15 245 Cm(n, f) 3.16 237 Np(n, f) 3.17 241 Am(n, f) 3.18 243 Am(n, f) 3.19 242m Am(n, f) Chapter 4: Inelastic Scattering 4.1 232 Th(n, n' 4.2 238 U(n, n') 4. 3 236 U(n, n') 4.…”

“…4 234 U(n, gamma) 5.5 238 Pu(n, gamma) 5. 6 240 Pu(n, gamma) 5.7 242 Pu(n, gamma) 5.8 242 Cm(n, gamma) 5.9 244 Cm(n, gamma) 5.10 235 U(n, gamma) 5.11 233 U(n, gamma) 5.12 239 Pu(n, gamma) 5.13 241 Pu(n, gamma) 5.14 243 Cm(n, gamma) 5.15 245 Cm(n, gamma) 5. 16 237 Np(n, gamma) 5.17 241 Am(n, gamma) 5.18 243 Am(n, gamma) 5.19 Chapter I…”

“…3 reaction -measured data at E n =14 MeV are higher than the neutron absorption cross section. The fission probability of 245 Cm, fissioning in the reaction 245 Cm(n,nf), was defined using data on 244 Cm(n,f) were defined by 242m Am(n,f) b…”

“…The NNDC produced preliminary uncertainties and correlation matrices for 15 actinides, including 233,234,236 U, 237 Np, 238,240,241,242 Pu, 241,242m,243 Am, 242,243,244,245 Cm [1,2]. These results are crosschecked by making comparisons with measured cross section data and newly calculated data for fission, capture, elastic, inelastic, (n,2n) cross sections and neutron multiplicities of major ( 232 Th, 235,,238 U, 239 Pu)…”