Fracture toughness evaluation of axially-cracked tubular thin-walled specimens of Zircaloy-4 and its implications for integrity analysis of nuclear fuel clad-Reference-Cited by-同舟云学术

Fracture toughness evaluation of axially-cracked tubular thin-walled specimens of Zircaloy-4 and its implications for integrity analysis of nuclear fuel clad

Published:2020-04 Issue: Volume:106 Page:102449
ISSN:0167-8442
Container-title:Theoretical and Applied Fracture Mechanics
language:en
Short-container-title:Theoretical and Applied Fracture Mechanics

Author:

Syed A.,Samal M.K.,Chattopadhyay J.,Dutta P.

Publisher

Elsevier BV

Subject

Applied Mathematics,Mechanical Engineering,Condensed Matter Physics,General Materials Science

Reference36 articles.

1. The Indian PHWR;Bajaj;Nucl. Eng. Des.,2006

2. R.N. Jayaraj, C. Ganguly, Recent developments in design and manufacture of uranium dioxide fuel pellets for PHWRs in India. Advanced fuel pellet materials and designs for water cooled reactors. Proceedings of a technical committee meeting held in Brussels, IAEA-TECDOC-1416, 20-24, 2003.

3. Effect of specimen thickness on fracture toughness;Lai;Eng. Fract. Mech.,1986

4. F.C. Allen, Effect of Thickness on the Fracture Toughness of 7075 Aluminum in the T6 and T73 Conditions. Damage Tolerance in Aircraft Structures, ASTM STP 486, American Society for Testing and Materials, 1971, pp. 16–38.

5. Standard test method for measurement of fracture toughness;ASTM Standard E 1820-01,2000

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Tube drawing analysis using upper bound and energy methods and validation by Cockcroft-Latham failure criteria;Journal of the Brazilian Society of Mechanical Sciences and Engineering;2021-12-08

2. The effect of oblique crack on stability and fracture properties of Cr-coated Zircaloy cladding;Annals of Nuclear Energy;2021-12

3. Effect of texture on crack initiation toughness and the corresponding anisotropy in ductile fracture resistance of thin Zircaloy-4 sheets of Indian PHWR core component;Journal of Nuclear Materials;2020-07