Comparison of the measured and predicted crack propagation behaviour of Zr–2.5Nb pressure tube material-Reference-Cited by-同舟云学术

Comparison of the measured and predicted crack propagation behaviour of Zr–2.5Nb pressure tube material

Published:2011-12 Issue:18 Volume:78 Page:3135-3152
ISSN:0013-7944
Container-title:Engineering Fracture Mechanics
language:en
Short-container-title:Engineering Fracture Mechanics

Author:

Williams B.W.,St Lawrence S.,Leitch B.W.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference45 articles.

1. CSA N285.8-05. Technical requirements for in-service evaluation of zirconium alloy pressure tubes in CANDU reactors. The Canadian Standards Association; 2005.

2. Davies PH, Hosbons RR, Griffiths M, Chow CK. Correlation between irradiated and unirradiated fracture toughness of Zr–2.5Nb pressure tubes. In: Garde AM, Bradley ER, editors. Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245. American Society for Testing and Materials; 1994. p. 135–67.

3. Davies PH, Himbeault DD, Shewfelt RSW, Hosbons RR. Crack growth resistance of irradiated Zr–2.5Nb pressure tube material at low hydrogen levels. In: Garde AM, Bradley ER, editors. Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245. American Society for Testing and Materials; 1994. p. 846–68.

4. Davies PH, Shewfelt RSW. Link between results of small- and large-scale toughness tests on irradiated Zr–2.5Nb pressure tube material. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. American Society for Testing and Materials; 1996. p. 492–517.

5. Davies PH, Shewfelt RSW. Size, geometry, and material effects in fracture toughness testing of irradiated Zr–2.5Nb pressure tube material. In: Sabol GP, Moan GD, editors. Zirconium in the nuclear industry: twelfth international symposium, ASTM STP 1354. American Society for Testing and Materials; 2000. p. 356–76.

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