Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
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Cheng-Der Wang
Abstract
To address the issue identified in USNRC’s Generic Letter (GL) 2003-01 that the unfiltered air in-leakage rate through plant’s control room envelope during design basis accident may exceed that assumed in the licensing analysis and thus threat the control room habitability, the control room envelope unfiltered in-leakage Tracer Gas Test (TGT) for Maanshan nuclear power plant (NPP) has been performed in 2020. For future applications, an improved control room dose analysis approach using Alternative Source Terms (AST) has been developed in present study to check whether the TGT results meet regulatory limits and have sufficient safety margins. The AST method follows Regulatory Guide 1.183 (RG 1.183) and the TGT results must be fulfilled the total effective dose criteria set forth in 10 CFR 50.67. Based on the AST approach and the TGT results, the control room personnel dose for Maanshan NPP during Loss of Coolant Accident (LOCA) is 14.35 mSv, and the safety margin is 71.3%. It is sufficient to cover the effects of structural ageing and changes in meteorological data during the control room habitability reassessment and the analysis uncertainty.
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Author contributions: The author has accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The author declares no conflicts of interest regarding this article.
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Articles in the same Issue
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Articles in the same Issue
- Frontmatter
- The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
- Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research
- Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation
- GRS contributions to flow-induced vibrations related activities in Europe
- Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
- Model of terminal debris bed formation after a CANDU core collapse
- Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump
- Study of the effect of virtual mass force on two-phase critical flow
- Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
- Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
- Lithium–lithium fusion evaporation research
- Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
- Events
