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Accident source term and radiological consequences of a small modular reactor

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Abstract

Considering the growing global demand for energy and the need for countries to achieve climate goals, there is an increasing global interest in small modular reactors (SMRs) and their applications. Accident source term and radiological consequence evaluations of SMRs are key components of nuclear and radiation safety reviews, which affect the site, exclusion area (EAB), and low population zone outer boundaries. Based on the design characteristics of the SMR and accident analysis results, a theoretical model of a whole-core fuel cladding damage accident was constructed to study the radioactivity released into the environment and its consequences. The accident source term and radiation dose calculation models were established to analyze the released amounts of radionuclides and the total effective dose affecting individuals at the site boundary. The results showed that the amount of radionuclides released into the environment after a whole-core fuel cladding damage accident reached 1014 Bq, among which the release amount of 133Xe was the largest. The total effective dose at the site boundary 30 days after the accident was 8.65 mSv. The highest total effective dose affecting individuals occurred to the east-north-east. The results of the accident source term and radiological consequence provide technical support for site boundary dose assessments and reviews of SMRs.

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Data availability

The data that support the findings of this study are openly available in Science Data Bank at https://doi.org/10.57760/sciencedb.j00186.00041 and http://resolve.pid21.cn/31253.11.sciencedb.j00186.00041.

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Authors and Affiliations

  1. Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing, 102401, China

    Hai-Ying Chen, Fu-Dong Liu, Shao-Wei Wang, Yi-Chuan Wang, Chao Xu & Qiao-Feng Liu

  2. State Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation, Beijing, 102401, China

    Hai-Ying Chen, Fu-Dong Liu & Chao Xu

Authors
  1. Hai-Ying Chen
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  2. Fu-Dong Liu
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  4. Yi-Chuan Wang
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  6. Qiao-Feng Liu
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Contributions

Methodology and conceptualization by Hai-Ying Chen and Fu-Dong Liu. Investigation was carried out by Fu-Dong Liu and Chao Xu. Calculations were run by Hai-Ying Chen, Yi-Chuan Wang, and Qiao-Feng Liu. Data collection and analysis were conducted by Hai-Ying Chen, Shao-Wei Wang, and Yi-Chuan Wang. The original draft was written by Hai-Ying Chen, Shao-Wei Wang, and Chao Xu. All authors reviewed and commented on previous versions of the manuscript. All authors read and agreed to the published version of the manuscript.

Corresponding authors

Correspondence to Shao-Wei Wang or Chao Xu.

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Chen, HY., Liu, FD., Wang, SW. et al. Accident source term and radiological consequences of a small modular reactor. NUCL SCI TECH 34, 40 (2023). https://doi.org/10.1007/s41365-023-01192-5

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  • DOI: https://doi.org/10.1007/s41365-023-01192-5

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