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2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
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.