BWR transient analysis with the coupled code system S3K/RELAP5-Reference-Cited by-同舟云学术

BWR transient analysis with the coupled code system S3K/RELAP5

Published:2011-07-01 Issue:3 Volume:76 Page:196-204
ISSN:2195-8580
Container-title:Kerntechnik
language:en
Short-container-title:

Author:

Jönsson C.¹,Moberg L.²,Grandi G.³,Judd J.⁴

Affiliation:

1. BSc in Irradiation and Health Physics, Studsvik Scandpower AB, Stensborgsgatan 4, 721 32 Västerås, Sweden. E-mail:

2. Ph.D. in Reactor Physics, Studsvik Scandpower AS, Gåsevikveien 2, 2027 Kjeller, Norway. E-mail:

3. Ph.D. in Nuclear Engineering, Studsvik Scandpower, Inc., 504 Shoup Avenue, Suite 201, Idaho Falls, ID 83402, USA. E-mail:

4. MSc in Nuclear Engineering, Studsvik Scandpower, Inc., 504 Shoup Avenue, Suite 201, Idaho Falls, ID 83402, USA. E-mail:

Abstract

Abstract This paper describes the coupled code system S3K-RELAP5 and the application of the code system to BWR transients without scram. In addition short descriptions are given for application of the coupled system to fast transients and rod drop accidents. The models and methods of the code system are presented. Validation results are shown for a recorded transient event in the Forsmark 3 reactor. It is concluded that S3K-RELAP5 adequately captures the complicated interaction between physical processes in the reactor as well as the essential reactor protection and control systems, which qualifies it for applications to fast and slow transients, with or without scram, and Reactivity Initiated Accidents (RIA).

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Link

https://www.degruyter.com/document/doi/10.3139/124.110151/pdf

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3. SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations;Nuclear Science and Engineering,2004

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