Pressurized Thermal Shock Analysis for Reactor Pressure Vessels

ZHENG Bin; ZANG Fenggang; SUN Yingxue

Mar. 2025

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ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13.

Citation:

ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13.

ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13.

Citation:

ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13.

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Pressurized Thermal Shock Analysis for Reactor Pressure Vessels

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2010-11-23
Rev Recd Date: 2011-02-21

Available Online: 2025-03-08

Abstract

Abstract

According to RCC-M rule and NRC 10CFR50.61,the PTS analysis was performed for the reactor pressure vessel beltline with assumed defect.The end of life reference temperature TR of nuclear power plant was calculated and assessed with PTS screening criteria.The stress intensity factors were calcu-lated under PTS transients and assessed with RCC-M Rule.
- Reactor,
- Pressure vessel,
- Fracture,
- Pressurized thermal shock,
- Stress intensity factor