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Latest News
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.
Gennadi Manturov
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE03-A2354
Articles are hosted by Taylor and Francis Online.
The data-processing system CONSYST/ABBN coupled with the ABBN-93 nuclear data library (NDL) was used in the analysis of BFS-62 and ZPPR JUPITER experiment series fast reactor mixed oxide cores, applying the Japan Nuclear Cycle Development Institute (JNC), Japan, core calculation code CITATION-FBR. The FFCP cell code was used to take into account the spatial cell heterogeneity and resonance effects based on the subgroup approach.The NDL effect has been studied by comparing the results calculated using the ABBN-93 nuclear data with the former ones obtained at JNC based on the JENDL-3.2 NDL. Calculation analysis results for the keff parameter for four BFS-62 cores as well as for three ZPPR JUPITER experiment series cores (ZPPR-9, ZPPR-13A, and ZPPR-17A) have been obtained. The estimated uncertainty in the keff values caused by possible errors in calculation of the applied corrections was estimated to be ~0.3% in the case of the ZPPR cores and 0.2% for the BFS-62 cores. The NDL effect determined by applying the ABBN-93 nuclear data in the JNC calculation route for the keff parameter appeared to be ~0.3% for the ZPPR and BFS-62 cores with plutonium. As for BFS-62 uranium-loaded cores, the NDL effect was ~0.1%. Sensitivity analysis was applied, and it has shown that the main contributors to the NDL effect are uranium, plutonium, and iron cross sections.This work is closely related to the JNC-Institute of Physics and Power Engineering, Russian Federation, collaboration on experimental investigation of excess weapon plutonium disposition in the BN-600 reactor using the BFS facility.