Published January 2007 | Version v1
Report

Development, qualification and application of the coupled RELAP5/PANTHER/COBRA code package for integrated PWR accident analysis

  • 1. Tractebel Engineering, Brussels (Belgium)

Description

At Tractebel Engineering (TE), a dynamic coupling has been developed between the best estimate thermal-hydraulics system code RELAP5 and the 3-dimensional neutronics code PANTHER via the transient analysis code linkage program TALINK. An interface between PANTHER and the subchannel core thermal-hydraulic analysis code COBRA 3C has been established for on-line calculation of the Departure from Nucleate Boiling Ratio. Since each client code has been qualified separately, the TE coupled code package has been qualified only by validation of the data exchange interface using OECD TMI-1 MSLB benchmark exercises. It has been then applied to develop a MSLB accident analysis methodology based on the TE deterministic bounding approach. The results of coupled thermal-hydraulic and neutronic analysis of SLB show that there exists an important margin in the traditional FSAR MSLB accident analysis. The methodology has been applied for MSLB accident analysis in support of licensing of the power uprate and steam generator replacement of the Doel 2 plant. The TE coupled code package will be applied for integrated safety analysis of other PWR accidents. (author)

Part of:
Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

Additional details

Publishing Information

ISBN
92-0-101207-1
Imprint Title
Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting
Imprint Pagination
321 p.
Journal Page Range
[18 p.]
ISSN
1011-4289
Report number
IAEA-TECDOC--1539(companion CD)

Conference

Title
Technical meeting on use and development of coupled computer codes for the analysis of accidents at nuclear power plants
Dates
26-28 Nov 2003
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
38096581
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; NUCLEATE BOILING; PWR TYPE REACTORS; REACTOR ACCIDENTS; SAFETY ANALYSIS; STEAM GENERATORS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; VALIDATION
Descriptors DEC
ACCIDENTS; BOILERS; BOILING; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
13 refs, 8 figs