Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA

Author:

Server William,Rosinski Stan,Lott Randy,Kim Charles,Weakland Dennis

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference19 articles.

1. Title 10 Code of Federal Register Part 50, Section 50.61. Fracture toughness requirements for protection against pressurized thermal shock events; June 14, 1991.

2. Brown C, Terek E, Conermann J, Les Bencini R. WCAP-15571. Analysis of capsule Y from first energy company Beaver Valley Unit 1 reactor vessel radiation surveillance program; November 2000.

3. ASTM Standard E 1921-97. Test method for the determination of reference temperature, T0, for ferritic steels in the transition range. 1998 Annual Book of ASTM Standards, vol. 03.01. West Conshohocken, PA: American Society for Testing and Materials.

4. Regulatory Guide 1.154. Format and content of plant-specific pressurized thermal shock safety analysis reports for pressurized water reactors, US Nuclear Regulatory Commission; January 1987.

5. Bishop BA, Frantz ER, Sloane BD, Wallace IT. WCAP-15156. WOG pilot-plant application of the EPRI alternative method for reactor vessel PTS; June 1999.

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