Summary of International PFM Round Robin analyses among Asian Countries on reactor pressure vessel integrity during pressurized thermal shock

2012 ◽  
Vol 90-91 ◽  
pp. 46-55 ◽  
Author(s):  
Y. Kanto ◽  
M.-J. Jhung ◽  
K. Ting ◽  
Y.-B. He ◽  
K. Onizawa ◽  
...  
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Round Robin ◽  
Reactor Pressure Vessel ◽  
Asian Countries ◽  
Pressurized Thermal Shock ◽  
Vessel Integrity ◽  
Reactor Pressure

Sensitive Analyses of Probabilistic Fracture Mechanics for Reactor Pressure Vessel during Pressurized Thermal Shock and Comparison with the Results of International Round Robin Analyses in Asian Countries

2011 ◽  
Vol 462-463 ◽  
pp. 878-883
Author(s):  
Yasuhiro Kanto ◽  
S. Yoshimura
Keyword(s):  
Fracture Mechanics ◽  
Thermal Shock ◽  
Pressure Vessel ◽  
Round Robin ◽  
Reactor Pressure Vessel ◽  
Asian Countries ◽  
Probabilistic Fracture Mechanics ◽  
Pressurized Thermal Shock ◽  
International Round ◽  
Reactor Pressure

This paper demonstrates sensitive analyses of probabilistic fracture mechanics (PFM) for reactor pressure vessel (RPV) during pressurized thermal shock (PTS) loading, and comparison of our calculation with the results of the international round robin (RR) analyses in Asian countries (Korea, Taiwan and Japan). The international Round Robin activity was performed in PFM sub-committees in the Atomic Energy Research Committee of Japan Welding Engineering Society (JWES) in conjunction with Korea and Taiwan research groups. The purposes of this program are to establish reliable procedures to evaluate fracture probability of reactor pressure vessels during pressurized thermal shock and to maintain the continuous cooperation among Asian institutes in the probabilistic approach to nuclear safety. Some parameters to RPV failure probabilities are chosen to evaluate their significance quantatively. The differences caused by selection of analyzing programs and some input parameters will be discussed.

Round robin analysis of pressurized thermal shock for reactor pressure vessel

2003 ◽  
Vol 226 (2) ◽  
pp. 141-154 ◽  
Author(s):  
Myung Jo Jhung ◽  
Seok Hun Kim ◽  
Jin Ho Lee ◽  
Youn Won Park
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Round Robin ◽  
Reactor Pressure Vessel ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock

2005 ◽  
Vol 19 (2) ◽  
pp. 634-648 ◽  
Author(s):  
Myung Jo Jhung ◽  
Changheui Jang ◽  
Seok Hun Kim ◽  
Young Hwan Choi ◽  
Hho Jung Kim ◽  
...  
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Structural Integrity ◽  
Round Robin ◽  
Reactor Pressure Vessel ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

Effects of Cladding on Reactor Pressure Vessel Integrity Based on the Revised PTS Rule (10 CFR 50.61)

2009 ◽  
Author(s):  
Vikram Marthandam ◽  
Timothy J. Griesbach ◽  
Jack Spanner
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Historical Perspective ◽  
Pressurized Thermal Shock ◽  
Asme Code ◽  
Potential Benefits ◽  
Vessel Integrity ◽  
Technical Basis ◽  
Reactor Pressure

This paper provides a historical perspective of the effects of cladding and the analyses techniques used to evaluate the integrity of an RPV subjected to pressurized thermal shock (PTS) transients. A summary of the specific requirements of the draft revised PTS rule (10 CFR 50.61) and the role of cladding in the evaluation of the RPV integrity under the revised PTS Rule are discussed in detail. The technical basis for the revision of the PTS Rule is based on two main criteria: (1) NDE requirements and (2) Calculation of RTMAX-X and ΔT30. NDE requirements of the Rule include performing volumetric inspections using procedures, equipment and personnel qualified under ASME Section XI, Appendix VIII. The flaw density limits specified in the new Rule are more restrictive than those stipulated by Section XI of the ASME Code. The licensee is required to demonstrate by performing analysis based on the flaw size and density inputs that the through wall cracking frequency does not exceed 1E−6 per reactor year. Based on the understanding of the requirements of the revised PTS Rule, there may be an increase in the effort needed by the utility to meet these requirements. The potential benefits of the Rule for extending vessel life may be very large, but there are also some risks in using the Rule if flaws are detected in or near the cladding. This paper summarizes the potential impacts on operating plants that choose to request relief from existing PTS Rules by implementing the new PTS Rule.

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
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