scholarly journals Demonstration of CFD to support the coupled analysis of a reactor pressure vessel subjected to pressurized thermal shock

2021 ◽  
Author(s):  
Yiqi Yu ◽  
Dillon Shaver ◽  
Elia Merzari
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Coupled Analysis ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

Computational studies on pressurized thermal shock in reactor pressure vessel

2021 ◽  
Vol 152 ◽  
pp. 107987
Author(s):  
Rakesh Chouhan ◽  
Anuj Kumar Kansal ◽  
Naresh Kumar Maheshwari ◽  
Avaneesh Sharma
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Computational Studies ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events

2014 ◽  
Author(s):  
Hsoung-Wei Chou ◽  
Chin-Cheng Huang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Shock ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Reactor Pressure Vessel ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

The failure probability of the pressurized water reactor pressure vessel for a domestic nuclear power plant in Taiwan has been evaluated according to the technical basis of the USNRC’s new pressurized thermal shock (PTS) screening criteria. The ORNL’s FAVOR code and the PNNL’s flaw models are employed to perform the probabilistic fracture mechanics analysis based on the plant specific parameters of the domestic reactor pressure vessel. Meanwhile, the PTS thermal hydraulic and the probabilistic risk assessment data analyzed from a similar nuclear power plant in the United States for establishing the new PTS rule are applied as the loading condition. Besides, an RT-based regression formula derived by the USNRC is also utilized to verify the through-wall cracking frequencies. It is found that the through-wall cracking of the analyzed reactor pressure vessel only occurs during the PTS events resulted from the stuck-open primary safety relief valves that later reclose, but with only an insignificant failure risk. The results indicate that the Taiwan domestic PWR reactor pressure vessel has sufficient structural margin for the PTS attack until either the end-of-license or for the proposed extended operation.

OS1410 Evaluation of Through-wall Cracking Frequency of Reactor Pressure Vessel under Pressurized Thermal Shock events

2013 ◽  
Vol 2013 (0) ◽  
pp. _OS1410-1_-_OS1410-3_
Author(s):  
Hiroyuki NISHIKAWA ◽  
Koichi MASAKI ◽  
Kazuya OSAKABE ◽  
Jinya KATSUYAMA ◽  
Kunio ONIZAWA
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

OS0809 Effects of Transient Type and Flaw Density on Through-wall Cracking Frequency of Reactor Pressure Vessel under Pressurized Thermal Shock Events

2014 ◽  
Vol 2014 (0) ◽  
pp. _OS0809-1_-_OS0809-3_
Author(s):  
Koichi MASAKI ◽  
Kazuya OSAKABE ◽  
Jinya KATSUYAMA ◽  
Genshichiro KATSUMATA ◽  
Kunio ONIZAWA
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure
Sign in / Sign up

Export Citation Format

Share Document