Probabilistic Fracture Mechanics Round Robin Analysis of Reactor Pressure Vessels during Pressurized Thermal Shock

被引：5

作者：

Jhung, Myung Jo ^{[1
]}

Kim, Seok Hun ^{[1
]}

Choi, Young Hwan ^{[1
]}

Chang, Yoon Suk ^{[2
]}

Xu, Xiangyuan ^{[3
]}

Kim, Jong Min ^{[4
]}

Kim, Jong Wook ^{[5
]}

Jang, Changheui ^{[6
]}

机构：

[1] Korea Inst Nucl Safety, Taejon 305338, South Korea

[2] Kyung Hee Univ, Yongin 446701, South Korea

[3] Sungkyunkwan Univ, Suwon 440746, South Korea

[4] Korea Power Engn Co, Taejon 305353, South Korea

[5] Korea Atom Energy Res Inst, Taejon 305353, South Korea

[6] Korea Adv Inst Sci & Technol, Taejon 305701, South Korea

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 2010年 / 47卷 / 12期

关键词：

pressurized thermal shock (PTS); reactor pressure vessel (RPV); structural integrity; stress intensity factor; warm prestressing (WPS); failure probability; inspection model; INTEGRITY;

D O I：

10.3327/jnst.47.1131

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In this study, round robin problems for the failure probabilities of a reactor pressure vessel are solved using the probabilistic fracture mechanics code. The flaw distribution and flaw density were modified to incorporate the effects of inspection quality. Then, the impact of the inspection quality and other key parameters on the failure probability was quantitatively evaluated. The results showed that the effect of inspection quality on the failure probability has the same characteristics irrespective of the two quite different transients and the wide range of fluence level. Overall, the various inspection qualities considered in this study resulted in about an order of magnitude difference in failure probability. Additionally, it was found that the effect of warm prestressing on the failure probability depends on the characteristics of the transients.

引用

页码：1131 / 1139

页数：9

共 50 条

[1] Round robin analysis of pressurized thermal shock for reactor pressure vessel
Jhung, MJ
Kim, SH
Lee, JH
Park, YW
NUCLEAR ENGINEERING AND DESIGN, 2003, 226 (02) : 141 - 154
[2] Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock
Jhung, MJ
Jang, C
Kim, SH
Choi, YH
Kim, HJ
Jung, S
Kim, JM
Sohn, GH
Jin, TE
Choi, TS
Kim, JH
Kim, JW
Park, KB
JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2005, 19 (02) : 634 - 648
[3] Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock
Myung Jo Jhung
Changheui Jang
Seok Hun Kim
Young Hwan Choi
Hho Jung Kim
Sunggyu Jung
Jong Min Kim
Gap Heon Sohn
Tae Eun Jin
Taek Sang Choi
Ji Ho Kim
Jong Wook Kim
Keun Bae Park
Journal of Mechanical Science and Technology, 2005, 19 : 634 - 648
[4] 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
Kanto, Y.
Yoshimura, S.
FRACTURE AND STRENGTH OF SOLIDS VII, PTS 1 AND 2, 2011, 462-463 : 878 - +
[5] Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During Pressurized Thermal Shock Events
Masaki, Koichi
Katsuyama, Jinya
Onizawa, Kunio
JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2014, 136 (01):
[6] Fracture mechanics analysis for reactor pressure vessel under pressurized thermal shock
Xu, Lei-Lei
Liang, Guo-Xing
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2014, 48 (11): : 2078 - 2084
[7] Pressurized thermal shock analysis for reactor pressure vessels
Zheng, Bin
Zang, Feng-Gang
Sun, Ying-Xue
Hedongli Gongcheng/Nuclear Power Engineering, 2012, 33 (01): : 1 - 3
[8] Influence factors of fracture mechanics analysis of reactor pressure vessel under pressurized thermal shock
Luo J.
Luo J.C.
Key Eng Mat, 2019, (333-339): : 333 - 339
[9] Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels
Katsuyama, Jinya
Osakabe, Kazuya
Uno, Shumpei
Li, Yinsheng
Yoshimura, Shinobu
JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2020, 142 (02):
[10] GUIDELINE ON PROBABILISTIC FRACTURE MECHANICS ANALYSIS FOR JAPANESE REACTOR PRESSURE VESSELS
Katsuyama, Jinya
Osakabe, Kazuya
Uno, Shumpei
Li, Yinsheng
Yoshimura, Shinobu
PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1B, 2017,

← 1 2 3 4 5 →