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Title: Evaluation of a consistent point-kinetics model for the TMI-1 MSLB benchmark problem

Abstract

The SAS-DIF3DK coupled code system is currently being used for analyzing the Three Mile Island Unit 1 (TMI-1) main-steam-line-break (MSLB) benchmark problem sponsored by the Organization for Economic Cooperation and Development Nuclear Energy Agency, the US Nuclear Regulatory Commission, and the Pennsylvania State University. The code uses the DIF3D-K spatial kinetics module for calculating the detailed core power evolution during the transient. The current analysis of the benchmark problem focuses on exercise 2, in which performance of three-dimensional, coupled neutronic/thermal-hydraulic codes is being evaluated. For this exercise, thermal-hydraulic boundary conditions are prescribed. Other exercises are defined to model the whole reactor system using point kinetics (exercise 1) and multidimensional kinetics (exercise 3) for calculating the power evolution. These exercises are useful for evaluating the accuracy of the point-kinetics schemes currently used in the nuclear industry for analyzing such transient scenarios.

Authors:
; ;  [1]
  1. Argonne National Lab., IL (United States)
Publication Date:
OSTI Identifier:
678156
Report Number(s):
CONF-990605-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 99:009141
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 80; Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: 1999
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; THREE MILE ISLAND-1 REACTOR; S CODES; REACTOR ACCIDENTS; MATHEMATICAL MODELS; EVALUATION; BENCHMARKS; REACTOR KINETICS; HEAT TRANSFER; HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS

Citation Formats

Taiwo, T.A., Dunn, F.E., and Cahalan, J.E. Evaluation of a consistent point-kinetics model for the TMI-1 MSLB benchmark problem. United States: N. p., 1999. Web.
Taiwo, T.A., Dunn, F.E., & Cahalan, J.E. Evaluation of a consistent point-kinetics model for the TMI-1 MSLB benchmark problem. United States.
Taiwo, T.A., Dunn, F.E., and Cahalan, J.E. Wed . "Evaluation of a consistent point-kinetics model for the TMI-1 MSLB benchmark problem". United States.
@article{osti_678156,
title = {Evaluation of a consistent point-kinetics model for the TMI-1 MSLB benchmark problem},
author = {Taiwo, T.A. and Dunn, F.E. and Cahalan, J.E.},
abstractNote = {The SAS-DIF3DK coupled code system is currently being used for analyzing the Three Mile Island Unit 1 (TMI-1) main-steam-line-break (MSLB) benchmark problem sponsored by the Organization for Economic Cooperation and Development Nuclear Energy Agency, the US Nuclear Regulatory Commission, and the Pennsylvania State University. The code uses the DIF3D-K spatial kinetics module for calculating the detailed core power evolution during the transient. The current analysis of the benchmark problem focuses on exercise 2, in which performance of three-dimensional, coupled neutronic/thermal-hydraulic codes is being evaluated. For this exercise, thermal-hydraulic boundary conditions are prescribed. Other exercises are defined to model the whole reactor system using point kinetics (exercise 1) and multidimensional kinetics (exercise 3) for calculating the power evolution. These exercises are useful for evaluating the accuracy of the point-kinetics schemes currently used in the nuclear industry for analyzing such transient scenarios.},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = ,
volume = 80,
place = {United States},
year = {1999},
month = {9}
}