Overview of the International Comparative Assessment Study of Pressurized Thermal-Shock in Reactor Pressure Vessels (RPV PTS ICAS)

Author:

Bass B.R,Pugh C.E,Sievers J,Schulz H

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference5 articles.

1. Final Report on the International Comparative Assessment Study of Pressurized-Thermal-Shock in Reactor Pressure Vessels. Organization for Economic Cooperation and Development, Paris, France, Report NEA/CSNI/R(99)3, 1999.

2. Schulz H, Sievers J, Bass BR, Pugh CE. Final Report on the International Comparative Assessment Study of Pressurized-Thermal-Shock in Reactor Pressure Vessels. Report GRS-152, Gesellschaft für Anlagen-und Reaktorsicherheit, Köln, Germany, October 1999.

3. Bass BR, Pugh CE, Schulz H, Sievers J. Final Report on the International Comparative Assessment Study of Pressurized-Thermal-Shock in Reactor Pressure Vessels. Report NUREG/CR-6651 (ORNL/TM-1999/231), Oak Ridge National Laboratory, December 1999.

4. Bass BR, Pugh CE, Keeney J, Schulz H, Sievers J. CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE). Report NUREG/CR-5997 (ORNL/TM-12307), Oak Ridge National Laboratory, December 1992, NEA/CSNI/R(94)12, GRS — 108, 1994.

5. Bass BR, Pugh CE, Keeney J, Schulz H, Sievers J. CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (FALSIRE II) (issued as three reports). NUREG/CR-6460 (ORNL/TM-13207), Oak Ridge National Laboratory, April 1996, NEA/CSNI/R (96) 1, 1996 and GRS — 130, 1996.

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