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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
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.