FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests-Reference-Cited by-同舟云学术

FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests

Published:2011-07 Issue:7 Volume:241 Page:2455-2461
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mikityuk K.,Shestopalov A.

Funder

Université de Genève

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

Reference18 articles.

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2. An uncertainty assessment methodology for materials behaviour in advanced fast reactors;Blanchet,2007

3. Advanced LMR safety analysis capabilities in the SASSYS-1 and SAS4A computer codes;Cahalan,1994

4. Joo, H.G., et al., 1998. PARCS, A multi-dimensional two-group reactor kinetics code based on the nonlinear nodal method. Technical report. PU/NE-98-26, Purdue University.

5. ODEPACK, a systematized collection of ODE solvers;Hindmarsh,1983

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