BWR-4 ATWS modeling with RELAP5-S3K-Reference-Cited by-同舟云学术

BWR-4 ATWS modeling with RELAP5-S3K

Published:2019-04 Issue: Volume:344 Page:38-45
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nikitin K.,Mueller P.,Bruder A.,Walser S.,Judd J.,Hiltbrand D.

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

Reference12 articles.

1. Guideline ENSI-A01, 2009. Requirements on the deterministic accident analysis for nuclear installations: scope, methodology and boundary conditions of the technical accident analysis (original written in German).

2. Hiltbrand, D., et al., 29.09.2015. SSP-12/312 Rev 9. RELAP5 Input Deck Description.

3. Hiltbrand, D., et al., 8.10.2015. SSP-12/313 Rev 9. RELAP5 Model Validation.

4. Ivanov, K., et al., 1999. Pressurized water reactor main steam line break benchmark: Volume I: Final specifications NEA/NSC/DOC(99)8, Nuclear Energy Agency Nuclear Science Committee.

5. BWR transient analysis with the coupled code system S3K/RELAP5;Jönsson;Kerntechnik,2011

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