This paper describes the current status and path forward of the ongoing activities in the Japan Society of Mechanical Engineers to implement reliability evaluation methodologies into the fast reactor codes and standards. The activities are going on on two aspects; design and inservice inspection. For design, methodologies are being developed to implement a reliability-based method for the evaluation of buckling of vessels using the Load and Resistance Factor Design method. With regards inservice inspection, in order to establish a methodology that takes account of the reliability of components when setting inspection requirements, evaluations are being performed on major passive components of fast reactors. To support the process, guidelines for reliability evaluation are being developed. The efforts to standardize reliability evaluation methodologies will be continued. One of the most important remaining issues is establishing a framework on which target reliabilities could be determined by the consensus of stakeholders.
- Nuclear Engineering Division
Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward
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Asayama, T, & Takaya, S. "Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T08A007. ASME. https://doi.org/10.1115/ICONE24-60936
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