Nonlinear numerical study of crack initiation and propagation in a reactor pressure vessel under pressurized thermal shock using XFEM

2017 ◽  
Vol 41 (2) ◽  
pp. 374-386 ◽  
Author(s):  
X. Sun ◽  
G. Chai ◽  
Y. Bao
Keyword(s):  
Crack Initiation ◽  
Thermal Shock ◽  
Pressure Vessel ◽  
Numerical Study ◽  
Reactor Pressure Vessel ◽  
Crack Initiation And Propagation ◽  
Initiation And Propagation ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

scholarly journals Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock

2021 ◽  
Vol 8 (1) ◽  
pp. 1-9
Author(s):  
Kuen Ting ◽  
Anh Tuan Nguyen ◽  
Kuen Tsann Chen ◽  
Li Hwa Wang ◽  
Yuan Chih Li ◽  
...  
Keyword(s):  
Crack Initiation ◽  
Thermal Shock ◽  
Conditional Probability ◽  
Pressure Vessel ◽  
Structural Integrity ◽  
Reactor Pressure Vessel ◽  
Term Operation ◽  
Oak Ridge ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

The beltline region is the most important part of the reactor pressure vessel, become embrittlement due to neutron irradiation at high temperature after long-term operation. Pressurized thermal shock is one of the potential threats to the integrity of beltline region also the reactor pressure vessel structural integrity. Hence, to maintain the integrity of RPV, this paper describes the benchmark study for deterministic and probabilistic fracture mechanics analyzing the beltline region under PTS by using FAVOR code developed by Oak Ridge National Laboratory. The Monte Carlo method was employed in FAVOR code to calculate the conditional probability of crack initiation. Three problems from Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel (PROSIR) round-robin analysis were selected to analyze, the present results showed a good agreement with the Korean participants’ results on the conditional probability of crack initiation.

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
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