Effects of curvature on ductile fracture initiation in curved compact tension specimens of hydrided irradiated Zr-2.5Nb materials with split circumferential hydrides

Author:

Sung Shin-JangORCID,Pan Jwo,St Lawrence Sterling,Scarth Douglas A.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference20 articles.

1. CSA N285.8-15. Technical requirements for in-service evaluation of zirconium alloy pressure tubes in CANDU reactors. Mississauga, ON, Canada: CSA Group; 2015.

2. Davies PH, Shewfelt RSW. Link between results of small- and large-scale toughness tests on irradiated Zr-2.5Nb pressure tube material. Zirconium in the nuclear industry: 11th international symposium. ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996. p. 492–517. .

3. Davies PH, Himbeault DD, Shewfelt RSW, Hosbons RR. Crack growth resistance of irradiated Zr-2.5Nb pressure tube material at low hydrogen levels. Effects of radiation on materials: 20th international symposium. ASTM STP 1405. West Conshohocken, PA: ASTM International; 2001. p. 846–68. .

4. St Lawrence S. Fracture toughness database for irradiated material. Private Communication, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada; 2012.

5. Leitch BW. Fracture analyses of an internally pressurized tube containing an axial, through-wall crack. Fatigue and Fracture Mechanics: 29th Volume, ASTM STP 1332, West Conshohocken, PA; 1999. p. 830–50. .

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