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WRC 386

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WRC 386 International Views on Reactor Pressure Vessel Integrity

Bulletin / Circular by Welding Research Council, 1993

Pressure Vessel Research Council

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The reports included in this Bulletin served as Appendices A through D in the White Paper on Reactor Vessel Integrity Requirements for Level A and B Conditions, which was prepared by the ASME Section XI Task Group on Reactor Vessel Integrity Requirements. WRC has elected to publish these reports because they provide an international perspective on nuclear plant safety issues.

The purpose of the Task Group was to examine the ASME Code requirements for reactor vessel integrity. As part of this effort, the historical basis of the current ASME Section III, Appendix G limits for plant operating criteria was reviewed.

With the benefit of advancing technology, the appropriateness of the existing Code requirements was re-examined.

The goals of the Task Group were toReview current regulations for material reference toughness, assumed reference flaw size, and plant operating criteria, and identify areas of conservatism and potential non-conservatism.Provide recommendations for determining plant operating pressure?temperature limits while maintaining the necessary requirements to assure vessel integrity. The full text of the ASME paper appears as WRC Bulletin 387 . It focuses primarily on pressurized water reactors rather than boiling water reactors, although information is provided for both types, and was prepared to document the basis for the current Section XI, Appendix G approach with recommendations for future Code improvements . The conclusions and recommendations provided, however, are generic and any application of them should be checked against plant specific considerations.

Publication of this document was sponsored by the Pressure Vessel Research Council of the Welding Research Council.

Reports Included:International Views on Reactor Pressure Vessel Integrity, Report No. 1 - Review of Procedures in the U.K. for the Assessment of Reactor Pressure Vessel Integrity By D. A. ScarthInternational Views on Reactor Pressure Vessel Integrity, Report No. 2 - U.S. and French Approaches to Reactor Pressure Vessel Integrity By T. Griesbach, C. Buchalet, W. L. ServerInternational Views on Reactor Pressure Vessel Integrity, Report No. 3 - Background of the Factors of Safety Used in Division 1 of Sections III and XI of the ASME Rules for Nuclear Vessels By W. E. CooperInternational Views on Reactor Pressure Vessel Integrity, Report No. 4 - The Russian Approach to Reactor Pressure Vessel Integrity By Y. Dragunov, G. I. Biryukov, A. N. Ivanov, Y. M. Maximov, and N. S. Fil