Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code-Reference-Cited by-同舟云学术

Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code

Published:2006-11 Issue:8 Volume:48 Page:806-819
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Bousbia Salah Anis,Vedovi Juswald,D'Auria Francesco,Galassi Giorgio,Ivanov Kostadin

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference15 articles.

1. Bousbia Salah, A., 2004. Overview of coupled system thermal–hydraulic-3D neutron kinetic code applications. PhD thesis, Ref: 17033. Università di Pisa.

2. Analysis of the peach bottom turbine trip 2 experiment by coupled RELAP5-PARCS 3D codes;Bousbia Salah;Nucl. Sci. Eng.,2004

3. Cerullo, N., D'Auria, F., Frogheri, F., Hinovsky, I., 1996. Data base for transient analyses in VVER1000 nuclear plants. In: ASME-JSME International Conference on Nuclear Engineering (ICONE-4), New Orleans (US), 10–14 March.

4. Code validation and uncertainties in system thermal–hydraulics;D'Auria;Prog. Nucl. Energy,1998

5. D'Auria, F., Galassi, G., Giannotti, W., 2002. Generic VVER 1000 MSLB sensitivity study. DIMNP NT 489(02) – rev. 0.

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