Analysis on Lift-Off experiment in Halden reactor by FEMAXI-6 code
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference13 articles.
1. S. Beguin, HWR-544, 1998
2. Analysis of mechanical load on cladding induced by fuel swelling during power ramp in high burn-up rod by fuel performance code FEMAXI-6
3. M. Suzuki, JAERI Data/Code 2000-030, 2000
4. Analysis of high burnup fuel behavior in Halden reactor by FEMAXI–V code
5. W. Wiesenack, M. Vankeerberghen, R. Thankappan, HWR-469, 1996
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4. Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions;Nuclear Technology;2006-09
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