Assessment of aging of Zr2.5Nb pressure tubes in CANDU™ reactors-Reference-Cited by-同舟云学术

Assessment of aging of Zr2.5Nb pressure tubes in CANDU™ reactors

Published:1997-07 Issue:1-3 Volume:171 Page:137-148
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Puls Manfred P.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference18 articles.

1. Role of microsegregation in fracture of cold-worked Zr2.5Nb pressure Tubes;Aitchison;J. Nucl. Mater.,1993

2. Prevention of delayed hydride cracking in zirconium alloys;Cheadle,1987

3. Locating a leaking crack by safe stimulation;Coleman;Int. J. Press. Vess. Piping,1990

4. Rejuvenation of fracture properties of irradiated Zr2.5Nb by heat treatment;Coleman,1992

5. Correlation between irradiated and unirradiated fracture toughness of Zr2.5Nb pressure tube material, Zirconium in the nuclear industry;Davies;ASTM Spec. Tech. Publ. 1245,1995

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