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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
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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Nuclear Science and Engineering
December 2025
Nuclear Technology
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November 2025
Latest News
Education and training to support Canadian nuclear workforce development
Along with several other nations, Canada has committed to net-zero emissions by 2050. Part of this plan is tripling nuclear generating capacity. As of 2025, the country has four operating nuclear generating stations with a total of 17 reactors, 16 of which are in the province of Ontario. The Independent Electricity System Operator has recommended that an additional 17,800 MWe of nuclear power be added to Ontario’s grid.
Jing Sun, Xueyao Shi, Qiaoyan Chen, Hui Wang
Nuclear Technology | Volume 211 | Number 12 | December 2025 | Pages 2947-2960
Research Article | doi.org/10.1080/00295450.2025.2517458
Articles are hosted by Taylor and Francis Online.
Analysis of the radioactive source terms in severe accidents is crucial for nuclear power plants, as it significantly influences the calculation of the offsite consequence and frequency of large radioactive releases. The International Atomic Energy Agency has emphasized that a representative accident scenario should be selected and verified for each release category when applying an integrated accident analysis code, although the specific guidelines remain unclear. In this study, the integrated severe accident analysis code MAAP has been adopted to calculate source term categories for the advanced China pressurized water reactor.
The release fractions of source terms to the environment from different severe accident sequences are calculated, compared, and analyzed for five important release categories. The results show that initiating events will not cause significant effects on source term results within one release category, though the mitigation measures may cause a difference of at least one magnitude for a bypass release category and a containment filtration release category. Recommendations for selecting representative severe accident scenarios are provided, which has important practical values for performing safety analyses for nuclear power plants.