Creep-fatigue design studies for a sodium-cooled fast reactor with tube sheet-to-shell structure subjected to elevated temperature service-Reference-Cited by-同舟云学术

Creep-fatigue design studies for a sodium-cooled fast reactor with tube sheet-to-shell structure subjected to elevated temperature service

Published:2010-03 Issue:3 Volume:24 Page:711-719
ISSN:1738-494X
Container-title:Journal of Mechanical Science and Technology
language:en
Short-container-title:J Mech Sci Technol

Author:

Koo Gyeong-Hoi,Lee Jae-Han

Publisher

Springer Science and Business Media LLC

Subject

Mechanical Engineering,Mechanics of Materials

Link

http://link.springer.com/content/pdf/10.1007/s12206-010-0121-1.pdf

Reference8 articles.

1. ASME Boiler and Pressure Vessel Code, Section III, Subsection NH, (2007).

2. RCC-MR, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, AFCEN (2002).

3. Elevated Temperature Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor, PNC N241-84-08, PNC, (1984).

4. G. H. Koo and B. Yoo, Elevated Temperature Design of KALIMER Reactor Internals Accounting for Creep and Stress Rupture Effects, Journal of the Korean Nuclear Society, 32(6) (2000) 566–594.

5. G. H. Koo and B. Yoo, Evaluation of Creep-Fatigue damage of KALIMER Reactor Internals Using the Elastic Analysis Method in RCC-MR, Journal of the Korean Nuclear Society, 33(6) (2001) 566–584.

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