Radiation safety is an important concern in the design and licensing of the 200MWe High Temperature Reactor Pebble-bed Module (HTR-PM) demonstration power plant in China. To meet the requirement of the regulatory, various radiation protection strategies and methods are applied in the design process of systems and components of HTR-PM. In this study, the radiation shielding design of HTR-PM is reviewed, which includes the radiation source analysis, in-house dose calculation tool, shielding and dose reduction methods used for primary systems. The underlying conservative assumption is also discussed for correctly evaluating the dose calculation result. This summary provides a relatively systematic review of the radiation shielding methods in the design phase of HTR-PM, which may provide useful information and experiences for the radiation shielding design of future pebble-bed reactors.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
Radiation Shielding Design of High Temperature Reactor Pebble-Bed Module (HTR-PM)
Sheng Fang,
Sheng Fang
Tsinghua University, Beijing, China
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Hong Li
Hong Li
Tsinghua University, Beijing, China
Search for other works by this author on:
Sida Sun
Tsinghua University, Beijing, China
Sheng Fang
Tsinghua University, Beijing, China
Hong Li
Tsinghua University, Beijing, China
Paper No:
ICONE24-60413, V004T11A005; 5 pages
Published Online:
October 25, 2016
Citation
Sun, S, Fang, S, & Li, H. "Radiation Shielding Design of High Temperature Reactor Pebble-Bed Module (HTR-PM)." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T11A005. ASME. https://doi.org/10.1115/ICONE24-60413
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