Analysis of high burnup fuel behavior in Halden reactor by FEMAXI–V code-Reference-Cited by-同舟云学术

Analysis of high burnup fuel behavior in Halden reactor by FEMAXI–V code

Published:2000-09 Issue:1 Volume:201 Page:99-106
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Motoe Suzuki

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

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4. Kier, P.H., Rabba, A.A., 1967. RABBLE, a program for computation of resonance absorption in multi-region reactor cells, ANL-7326.

5. Kosaka, Y., 1993. Thermal conductivity degradation analysis of the ultra high burnup experiment (IFA-562), HWR-341.

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1. A review of fuel performance modelling;Journal of Nuclear Materials;2019-04

2. An empirical formulation to describe the evolution of the high burnup structure;Journal of Nuclear Materials;2015-01

3. BWR fuel rod behavior evaluation for preconditioning power ramps with FEMAXI-V;Annals of Nuclear Energy;2011-10

4. Analysis of Reactor Fuel Rod Behavior;Handbook of Nuclear Engineering;2010

5. Extension of the TRANSURANUS burn-up model;Journal of Nuclear Materials;2008-05