SIMULATE-3 K coupled code applications

Author:

Jönsson C.1,Grandi G.2,Judd J.3

Affiliation:

1. 1(BSc), Studsvik Scandpower AB, Stensborgsgatan 4, 72132 Västerås, Sweden, E-mail: christian.jonsson@studsvik.com

2. 2(Ph.D.), E-mail: gerardo.grandi@studsvik.com, Studsvik Scandpower, Inc., 1070 Riverwalk Drive, Suite 150, Idaho Falls, ID 83402-3345, USA

3. 3(MSc), E-mail: jerry.judd@studsvik.com, Studsvik Scandpower, Inc., 1070 Riverwalk Drive, Suite 150, Idaho Falls, ID 83402-3345, USA

Abstract

AbstractThis paper describes the coupled code system TRACE/SIMULATE-3 K/VIPRE and the application of this code system to the OECD PWR Main Steam Line Break. A short description is given for the application of the coupled system to analyze DNBR and the flexibility the system creates for the user. This includes the possibility to compare and evaluate the result with the TRACE/SIMULATE-3K (S3K) coupled code, the S3K standalone code (core calculation) as well as performing single-channel calculations with S3K and VIPRE. This is the typical separate-effect-analyses required for advanced calculations in order to develop methodologies to be used for safety analyses in general. The models and methods of the code systems are presented. The outline represents the analysis approach starting with the coupled code system, reactor and core model calculation (TRACE/S3K). This is followed by a more detailed core evaluation (S3K standalone) and finally a very detailed thermal-hydraulic investigation of the hot pin condition (VIPRE).

Publisher

Walter de Gruyter GmbH

Subject

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

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