FUEL PERFORMANCE CODE COSMOS FOR ANALYSIS OF LWR UO2AND MOX FUEL
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference11 articles.
1. Cosmos: A computer code to analyze LWR UO2 and MOX fuel up to high burnup
2. Investigations on swelling and fission gas behaviour in uranium dioxide
3. The effect of cladding restraint on fission gas release behavior
4. Analysis of fission gas release and gaseous swelling in UO2 fuel under the effect of external restraint
5. Fission Gas Release during Post Irradiation Annealing of BWR Fuels
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2. Fabrication of micro-cell UO2–Mo pellet with enhanced thermal conductivity;Journal of Nuclear Materials;2015-07
3. Abnormal Crowd Motion Detection Using Double Sparse Representations;Lecture Notes in Computer Science;2015
4. A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments;Nuclear Science and Engineering;2014-10
5. Implementation of effective-stress-function algorithm for nuclear fuel performance code;International Journal of Precision Engineering and Manufacturing;2013-05
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