Behaviour of irradiated PHWR fuel pins during high temperature heating-Reference-Cited by-同舟云学术

Behaviour of irradiated PHWR fuel pins during high temperature heating

Published:2008-12 Issue:1-2 Volume:383 Page:122-127
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Viswanathan U.K.,Unnikrishnan K.,Mishra Prerna,Banerjee Suparna,Anantharaman S.,Sah D.N.

Publisher

Elsevier BV

Subject

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

Reference5 articles.

1. H.M. Chung, T.F. Kassner, Embrittlement criteria for zircaloy fuel cladding applicable to accident situations in light-water reactors: summary report, NUREG/CR-1344 (ANL-79-48), US Nuclear Regulatory Commission, 1980.

2. D.N. Sah, U.K. Viswanathan, K. Unnikrishnan, Prerna Mishra, R.S. Shriwastaw, S. Anantharaman, Post-irradiation examination of high burn up PHWR fuel bundle 56504 from KAPS-1, Report BARC/2007/E/002, Bhabha Atomic Research Centre, Mumbai, India.

3. U.K. Viswanathan, S. Anantharaman, K.C. Sahoo, Measurement of fission gas release from irradiated nuclear fuel elements, Report BARC/2005/E/026, Bhabha Atomic Research Centre, Mumbai, India.

4. E. Hindle, D. Worswick, in: D.G. Franklin, R.B. Adamson (Eds.), Zirconium in the Nuclear Industries: Sixth International Symposium, STP 824, ASTM, Philadelphia, 1984, p. 133.

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