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Overview of the Japanese Code of Surveillance Test Program for Reactor Vessels

[+] Author Affiliations
Minoru Tomimatsu, Seiji Asada

Mitsubishi Heavy Industries, Ltd., Kobe, Japan

Hitoshi Ohata

The Japan Atomic Power Company, Tokyo, Japan

Hideo Kobayashi

Yokohama National University, Yokohama, Japan

Paper No. PVP2006-ICPVT-11-93785, pp. 443-450; 8 pages
doi:10.1115/PVP2006-ICPVT-11-93785
From:
  • ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
  • Volume 1: Codes and Standards
  • Vancouver, BC, Canada, July 23–27, 2006
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4752-7 | eISBN: 0-7918-3782-3
  • Copyright © 2006 by ASME

abstract

The Japan Electric Association Code, JEAC 4201, “Method of Surveillance Tests for Structural Materials of Nuclear Reactors” was originally published in 1970 so as to design a surveillance program for monitoring radiation induced changes in mechanical properties of beltline materials in light-water moderated nuclear power reactor vessels and to evaluate the test results. Recently in 2004 the code was revised, and a new method for predicting the decrease in upper shelf Charpy impact energy (USE) of beltline materials was incorporated based on the results of the research performed as a national project by the Japan Power Engineering and Inspection Corporation. Japanese surveillance tests program, including materials selections, type of specimens, number of capsules, withdrawal schedule, and evaluation of the results, is overviewed. Furthermore, methods for predicting the decrease in USE and reference temperature shift for beltline materials are also presented.

Copyright © 2006 by ASME

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