This paper describes the outline of the guidelines on structural reliability evaluation for the passive components of the fast breeder reactor (FBR). The guidelines are now being prepared by the task force for the system based code in the Japan society of mechanical engineers in order to contribute to reducing differences in evaluated structural reliability by evaluators. They consist of five chapters, which are “General rules”, “Reliability evaluation”, “Failure scenario setting”, “Modeling”, and “Failure probability calculation”, respectively. In the chapter of “Reliability evaluation”, the general procedures of reliability evaluation are explained. Detailed procedures at each step are explained in the following chapters in the guidelines. Evaluation procedures for accumulation damage and crack propagation due to creep-fatigue interaction which is a typical degradation phenomenon in FBR are also provided in the appendix of the guidelines. In addition, some examples of random variables are prepared as standard input data for structural reliability evaluation.
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4589-9
PROCEEDINGS PAPER
Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR
Shigeru Takaya,
Shigeru Takaya
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Search for other works by this author on:
Hideo Machida,
Hideo Machida
Tepco Systems Corporation, Tokyo, Japan
Search for other works by this author on:
Yoshio Kamishima
Yoshio Kamishima
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Search for other works by this author on:
Shigeru Takaya
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Hideo Machida
Tepco Systems Corporation, Tokyo, Japan
Yoshio Kamishima
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Paper No:
ICONE22-30570, V001T07A005; 4 pages
Published Online:
November 17, 2014
Citation
Takaya, S, Machida, H, & Kamishima, Y. "Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T07A005. ASME. https://doi.org/10.1115/ICONE22-30570
Download citation file:
9
Views
0
Citations
Related Proceedings Papers
Related Articles
Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
ASME J of Nuclear Rad Sci (January,2015)
A State-of-the-Art Review of Fatigue Life Prediction Models for Solder Joint
J. Electron. Packag (December,2019)
Dynamic Reliability Evaluation of Nonrepairable Multistate Weighted k -Out-of- n System With Dependent Components Based on Copula
ASME J. Risk Uncertainty Part B (December,2018)
Related Chapters
Impact of CCF Assumptions on PSA and PSA Application Calculations (PSAM-0172)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Start-Up, Shutdown, and Lay-Up
Consensus on Pre-Commissioning Stages for Cogeneration and Combined Cycle Power Plants