GUIDELINE ON PROBABILISTIC FRACTURE MECHANICS ANALYSIS FOR JAPANESE REACTOR PRESSURE VESSELS

被引:0
|
作者
Katsuyama, Jinya [1 ]
Osakabe, Kazuya [2 ]
Uno, Shumpei [1 ]
Li, Yinsheng [1 ]
Yoshimura, Shinobu [3 ]
机构
[1] Japan Atom Energy Agcy, 2-4 ShiraneShirakata, Tokai, Ibaraki 3191195, Japan
[2] Mizuho Informat & Res Inst, Chiyoda Ku, 2-3 Kanda Nishikicho, Tokyo 1018443, Japan
[3] Univ Tokyo, Bunkyo Ku, 7-3-1 Hongo, Tokyo, Japan
关键词
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
In Japan, to prevent nil-ductile fracture of reactor pressure vessels (RPVs) due to neutron irradiation embrittlement, deterministic fracture mechanics evaluation in accordance with the standards developed by the Japan Electric Association is performed for assessing the structural integrity of RPVs under pressurized thermal shock (PTS) events considering neutron irradiation embrittlement. In recent years, a structural integrity assessment methodology based on probabilistic fracture mechanics (PFM) has been introduced into the regulations in the United States and a few European countries. PFM is a rational methodology for evaluating the failure frequency of important pressure boundary components by considering the statistical distributions of various influence factors related to ageing due to the long-term operation. At Japan Atomic Energy Agency (JAEA), a PFM analysis code called PASCAL has been developed to evaluate the failure frequency of RPVs considering neutron irradiation embrittlement and PTS events. In addition, JAEA has developed a guideline for the. PFM based structural integrity assessment of RPVs to promote the applicability of PFM in Japan and achieve the objective that an engineer/analyst who familiar with the fracture mechanics to perform PFM analyses and evaluate through-wall cracking frequency (TWCF) of RPVs easily. The guideline consists of a main body (general requirements), explanation (guidance), and several supplements. The technical basis for PFM analysis is also provided, and the new information and better fracture mechanics models are included in the guideline. In this paper, an overview of the guideline and some typical analysis results obtained based on the guideline and the Japanese database related to PTS evaluation are presented.
引用
收藏
页数:9
相关论文
共 50 条
  • [1] 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):
  • [2] PROBABILISTIC FRACTURE MECHANICS ANALYSIS MODELS FOR JAPANESE REACTOR PRESSURE VESSELS
    Lu, Kai
    Katsuyama, Jinya
    Uno, Shumpei
    Li, Yinsheng
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1B, 2017,
  • [3] DEVELOPMENT OF CRACK EVALUATION MODELS FOR PROBABILISTIC FRACTURE MECHANICS ANALYSES OF JAPANESE REACTOR PRESSURE VESSELS
    Lu, Kai
    Masaki, Koichi
    Katsuyama, Jinya
    Li, Yinsheng
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 1B, 2019,
  • [4] Improvements on Evaluation Functions of a Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessels
    Lu, Kai
    Katsuyama, Jinya
    Li, Yinsheng
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2020, 142 (02):
  • [5] Recent improvements of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessels
    Lu, Kai
    Takamizawa, Hisashi
    Katsuyama, Jinya
    Li, Yinsheng
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2022, 199
  • [6] Probabilistic fracture mechanics:: application in reactor pressure vessels and oil pipelines
    Martinez Trinidad, Jose
    Samayoa Ochoa, Didier
    Hernandez Garcia, Erika
    Silva Lomeli, Jose de Jesus
    Susarrey Huerta, Orlando
    Balankin, Alexander
    REVISTA MEXICANA DE FISICA, 2005, 51 (01) : 19 - 29
  • [7] APPLICATION OF PROBABILISTIC FRACTURE MECHANICS METHODOLOGY FOR JAPANESE REACTOR PRESSURE VESSELS USING PASCAL4
    Lu, Kai
    Katsuyama, Jinya
    Li, Yinsheng
    Yoshimura, Shinobu
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2019, VOL 1, 2019,
  • [8] DEVELOPMENT OF PROBABILISTIC FRACTURE MECHANICS ANALYSIS CODE PASCAL VERSION 4 FOR REACTOR PRESSURE VESSELS
    Lu, Kai
    Masaki, Koichi
    Katsuyama, Jinya
    Li, Yinsheng
    Uno, Shumpei
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 1B, 2019,
  • [9] COUPLING OF NEUTRON TRANSPORT AND PROBABILISTIC FRACTURE MECHANICS CODES FOR ANALYSIS OF EMBRITTLED REACTOR PRESSURE VESSELS
    Spencer, Benjamin W.
    Hoffman, William M.
    Collins, Benjamin S.
    Henderson, Shane C.
    PROCEEDINGS OF THE ASME 2020 PRESSURE VESSELS & PIPING CONFERENCE (PVP2020), VOL 3, 2020,
  • [10] Modular system for probabilistic fracture mechanics analysis of embrittled reactor pressure vessels in the Grizzly code
    Spencer, B. W.
    Hoffman, W. M.
    Backman, M. A.
    NUCLEAR ENGINEERING AND DESIGN, 2019, 341 : 25 - 37