Japanese Activities Concerning Nuclear Codes and Standards—Part I

[+] Author and Article Information
Yasuhide Asada

 Thermal and Nuclear Power Engineering Society, Terayama Pacific Bldg, 1-23-11 Toranomon, Minato-ku, Tokyo 105-0001 Japanasada@tenpes.or.jp

J. Pressure Vessel Technol 128(1), 57-63 (Oct 19, 2005) (7 pages) doi:10.1115/1.2138062 History: Received September 01, 2005; Revised October 19, 2005

This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part I of the series includes an overview, a discussion of administrative and design aspects related to new methods of evaluating the integrity of components, that is, piping seismic rules based on ratcheting fatigue, a fracture toughness equation for vessel materials, an extension of the Ke factor based on elastic follow-up, a discussion of high cycle thermal fatigue, and a three-dimensional finite element method elastic-plastic analysis procedure.

Copyright © 2006 by American Society of Mechanical Engineers
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Figure 1

Photographs of the test devices, here testing bent pipe. (a) Static cyclic test, (b) dynamic test.

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Figure 2

Relationship between fracture toughness and T-RTNDT. Ref. 32.

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Figure 3

Ke evaluation comparison

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Figure 4

Evaluation flow chart for thermal striping in a mixing tee with hot and cold water

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Figure 5

Evaluation flow chart for thermal stratification in a branch pipe with a closed end

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Figure 6

Flow of the strength evaluation method without stress classification

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Figure 7

Example of determination of the cyclic yield area




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