Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup-Reference-Cited by-同舟云学术

Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup

Published:2009-08 Issue:3 Volume:392 Page:545-551
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Viswanathan U.K.,Sah D.N.,Rath B.N.,Anantharaman S.

Publisher

Elsevier BV

Subject

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

Reference22 articles.

1. D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, Chapter 15 on Fission Gas Release, TID 26711-P1, US Department of Energy, 1976.

2. Investigations on swelling and fission gas behaviour in uranium dioxide

3. M. Lippens, D. Boulanger, L. Martens, Industry challenges and expectations with respect to fission gas release, in: Proceedings of Seminar on Fission Gas Behaviour in Water Reactor Fuels, Cadarache, France, September 26–29, 2000, pp. 31–45.

4. U.K. Viswanathan, S. Anantharaman, D.N. Sah, S. Chatterjee, K.C. Sahoo, D.S.C. Purushotham, Studies on the fission gas release behaviour of BWR and experimental MOX fuel elements, in: Proceedings of Seminar on Fission Gas Behaviour in Water Reactor Fuels, Cadarache, France, September 26–29, 2000, pp. 107–115.

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