Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings-Reference-Cited by-同舟云学术

Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings

Published:2008-02 Issue:1-3 Volume:373 Page:415-423
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Hózer Zoltán,Győri Csaba,Matus Lajos,Horváth Márta

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference19 articles.

1. Ballooning Experiments with VVER Cladding

2. Cladding tube deformation and core emergency cooling in a loss of coolant accident of a pressurized water reactor

3. G. Hache, H.M. Chung, in: NUREG/CP-0172, 2001, p. 205.

4. D.O. Hobson, in: Proceedings of the ANS Topical Meeting on Water Reactor Safety, Salt Lake City, 1973, p. 274.

5. Yu.K. Bibilashvili, N.B. Sokolov, L.N. Andreeva-Andrievskaya, V.Yu. Tonkov, A.V. Salatov, A.M. Morosov, V.P. Smirnov, in: IAEA-TECDOC-1320, International Atomic Energy Agency, 2002, p. 186.

Cited by 51 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. Performance analysis of zirconium alloy after long-term cooling after simulated LOCA test;Nuclear Engineering and Design;2024-08

2. A thermogravimetric comparative study of the high temperature steam oxidation of bare and pre-oxidized Zircaloy-4, M5Framatome and Optimized ZIRLO™;Journal of Nuclear Materials;2024-08

3. Performance Analysis of Zirconium Alloy after Long-Term Cooling after Simulated Loca Test;2024

4. Numerical Simulation of Fuel Pellet Cladding Interaction in Nuclear Reactor;Environmental Science and Engineering;2024

5. Effect of Cr coating on the mechanical integrity of Accident Tolerant Fuel cladding under ring compression test;Journal of Nuclear Materials;2023-11