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Development of Material and Structural Reliability Evaluation System MSS-REAL

[+] Author Affiliations
Tai Asayama, Masaki Morishita

Japan Atomic Energy Agency, Oarai, Ibaraki, Japan

Takehiko Kato

Joyo Industries, Ltd., Oarai, Ibaraki, Japan

Paper No. ICONE14-89760, pp. 673-678; 6 pages
doi:10.1115/ICONE14-89760
From:
  • 14th International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management
  • Miami, Florida, USA, July 17–20, 2006
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4242-8 | eISBN: 0-7918-3783-1
  • Copyright © 2006 by ASME

abstract

For the development of the System Based Code, which was proposed by Asada and intends to optimize structural design of nuclear components by enabling margin exchange between various technical options, a tool for life cycle structural reliability evaluation method is necessary. For this purpose, the authors are developing a material strength and structural reliability evaluation system MSS-REAL. The system is primarily for fast breeder reactors but its methodologies can also be applied to the other types of reactors. This paper summarizes the features of the MSS-REAL system with examples and also describes a future development plan.

Copyright © 2006 by ASME
Topics: Reliability

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