SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations

Belblidia, Lotfi A; Grandi, Gerardo M; Joensson, Christian

Title: SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations

Full Record
Other Related Research

Abstract

This paper discusses the model and results for the Peach Bottom 2 Turbine Trip Test 2 using Studsvik Scandpower's transient code SIMULATE-3K. All data pertaining to core, vessel, and scenario were taken from the NEA/OECD BWR benchmark specifications. Nuclear data were generated with Studsvik Scandpower's lattice code CASMO-4 and core analysis code SIMULATE-3. Comparisons to measured data, sensitivity to model options and data, as well as results from more limiting scenarios are presented. SIMULATE-3K captures well the pressure wave propagation, void collapse during the pressurization phase, and resulting power excursion.

Authors:

Belblidia, Lotfi A ^[1]; Grandi, Gerardo M ^[1]; Joensson, Christian ^[2]

Studsvik Scandpower Inc. (Sweden)
Studsvik Scandpower AB (Sweden)

Publication Date:: Fri Oct 15 00:00:00 EDT 2004

OSTI Identifier:: 20808394

Resource Type:: Journal Article

Journal Name:: Nuclear Science and Engineering

Additional Journal Information:: Journal Volume: 148; Journal Issue: 2; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0029-5639

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; BENCHMARKS; BWR TYPE REACTORS; EXCURSIONS; NEA; PRESSURIZATION; REACTOR CORES; REACTOR VESSELS; SENSITIVITY; SPECIFICATIONS; TRANSIENTS; TURBINES; VOIDS; WAVE PROPAGATION

Citation Formats


                    Belblidia, Lotfi A, Grandi, Gerardo M, and Joensson, Christian. SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations.  United States: N. p., 2004. 
        Web.

Copy to clipboard


                    Belblidia, Lotfi A, Grandi, Gerardo M, & Joensson, Christian. SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations.  United States.

Copy to clipboard


                    Belblidia, Lotfi A, Grandi, Gerardo M, and Joensson, Christian. 2004.  
        "SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations".  United States.

Copy to clipboard


                    
@article{osti_20808394,

  title        = {SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations},

  author       = {Belblidia, Lotfi A and Grandi, Gerardo M and Joensson, Christian},

  abstractNote = {This paper discusses the model and results for the Peach Bottom 2 Turbine Trip Test 2 using Studsvik Scandpower's transient code SIMULATE-3K. All data pertaining to core, vessel, and scenario were taken from the NEA/OECD BWR benchmark specifications. Nuclear data were generated with Studsvik Scandpower's lattice code CASMO-4 and core analysis code SIMULATE-3. Comparisons to measured data, sensitivity to model options and data, as well as results from more limiting scenarios are presented. SIMULATE-3K captures well the pressure wave propagation, void collapse during the pressurization phase, and resulting power excursion.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/20808394},
  journal      = {Nuclear Science and Engineering},

  issn         = {0029-5639},

  number       = 2,

  volume       = 148,

  place        = {United States},

  year         = {Fri Oct 15 00:00:00 EDT 2004},

  month        = {Fri Oct 15 00:00:00 EDT 2004}

}

Copy to clipboard

Journal Article:

Other availability

Find in Google Scholar

Search WorldCat to find libraries that may hold this journal

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

Peach Bottom Turbine Trip Simulations with RETRAN Using INER/TPC BWR Transient Analysis Method

Journal Article Lainsu, Kao; Chiang, Show-Chyuan - Nuclear Technology

The work described in this paper is benchmark calculations of pressurization transient turbine trip tests performed at the Peach Bottom boiling water reactor (BWR). It is part of an overall effort in providing qualification basis for the INER/TPC BWR transient analysis method developed for the Kuosheng and Chinshan plants. The method primarily utilizes an advanced system thermal hydraulics code, RETRAN02/MOD5, for transient safety analyses. Since pressurization transients would result in a strong coupling effect between core neutronic and system thermal hydraulics responses, the INER/TPC method employs the one-dimensional kinetic model in RETRAN with a cross-section data library generated by themore »« less
Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System

Journal Article Ui, Atsushi; Miyaji, Takamasa - Nuclear Science and Engineering

The best-estimate coupled three-dimensional (3-D) core and thermal-hydraulic code system TRAC-BF1/COS3D has been developed. COS3D, based on a modified one-group neutronic model, is a 3-D core simulator used for licensing analyses and core management of commercial boiling water reactor (BWR) plants in Japan. TRAC-BF1 is a plant simulator based on a two-fluid model. TRAC-BF1/COS3D is a coupled system of both codes, which are connected using a parallel computing tool. This code system was applied to the OECD/NRC BWR Turbine Trip Benchmark. Since the two-group cross-section tables are provided by the benchmark team, COS3D was modified to apply to this specification.more »« less
Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS Three-Dimensional Codes

Journal Article Bousbia-Salah, Anis; Vedovi, Juswald; D'Auria, Francesco; ... - Nuclear Science and Engineering

Thanks to continuous progress in computer technology, it is now possible to perform best-estimate simulations of complex scenarios in nuclear power plants. This method is carried out through the coupling of three-dimensional (3-D) neutron modeling of a reactor core into system codes. It is particularly appropriate for transients that involve strong interactions between core neutronics and reactor loop thermal hydraulics. For this purpose, the Peach Bottom boiling water reactor turbine trip test was selected to challenge the capability of such coupled codes. The test is characterized by a power excursion induced by rapid core pressurization and a self-limiting course behavior.more »« less
Simulation of Peach Bottom turbine trip transients TT1, TT2 and TT3 with SIMULATE-3K

Conference Henry, Chris; Ivanov, Boyan; Grandi, Gerardo

The Peach Bottom 2 Turbine Trip transients tests TT1, TT2 and TT3 are simulated with SIMULATE-3K. This work provides the initial basis for evaluation of the capabilities and accuracy of coupled 3D neutronics/thermal hydraulics best estimate calculations for support of safety analysis. Selected results, obtained with SIMULATE-3K, are compared to available measurements and benchmark results. The comparisons are analyzed and the application of SIMULATE-3K for best estimate analysis approach within the safety analysis methodology is discussed. (authors)
RAMONA analysis of the Peach Bottom-2 turbine trip transients. Final report

Technical Report Moberg, L; Rasmussen, J; Sauar, T; ...

This report documents the RAMONA computer code analysis of three turbine trip tests performed at the Peach Bottom-2 BWR in 1977. Utilizing the point kinetics model and the one-dimensional and three-dimensional (3-D) neutron kinetics models, the RAMONA simulations present experimental data on severe pressurization transients in a BWR. Emphasis is placed on the systematic comparison between different core model approximations and on specific results from the 3-D simulation using the neutron kinetics model.

Similar Records