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The current status of heat pipe R&D
Idaho National Laboratory under the Department of Energy–sponsored Microreactor Program recently conducted a comprehensive phenomena identification and ranking table (PIRT) exercise aimed at advancing heat pipe technology for microreactor applications.
Vladimir M. Maslov, Yasuyuki Kikuchi
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 492-497
Technical Note | doi.org/10.13182/NSE96-A17927
Articles are hosted by Taylor and Francis Online.
A statistical model is used to interpret the available 232U(n,f) cross-section data in the neutron energy range from 0.003 to 7.4 MeV Below an incident neutron energy of ≈ 1 MeV, the nonthreshold energy dependence of the 232U(n,f) cross section is interpreted in a double-humped fission barrier model, the inner barrier of fissioning nucleus being ≈1 MeV lower than the outer one, as anticipated with the shell correction method calculation.
