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Title: Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.

Abstract

To allow the detailed analysis of the two-phase coolant flow and heat transfer phenomena in a boiling water reactor fuel bundle the CFD-BWR model is being developed for use with the commercial code STAR-CD which provides general two-phase flow modeling capabilities. The paper reviews the key boiling phenomenological models, describes the overall strategy adopted for the combined CFD-BWR and STAR-CD boiling models validation and presents results of a set of experiment analyses focused on the validation of specific models implemented in the code. The location of vapor generation onset, axial temperature profile and axial and radial void distributions were calculated and compared with experimental data. Good agreement between computed and measured results was obtained for a large number of test cases.

Authors:
; ; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
944030
Report Number(s):
ANL/NE/CP-118830
TRN: US0900502
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: OECD/NEA International & IAEA Workshop (CFD4NRS); Sep. 5, 2006 - Sep. 7, 2006; Garching, Munich, Germany
Country of Publication:
United States
Language:
ENGLISH
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BOILING; COMPUTERIZED SIMULATION; COOLANTS; FLUID MECHANICS; HEAT TRANSFER; IAEA; NUCLEAR FUELS; SIMULATION; TWO-PHASE FLOW; VALIDATION; WATER

Citation Formats

Ustinenko, V., Samigulin, M., Ioilev, A., Lo, S., Tentner, A., Lychagin, A., Razin, A., Girin, V., Vanyukov, Ye., Nuclear Engineering Division, Russian Russian Federation, and CD-adapco. Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.. United States: N. p., 2007. Web.
Ustinenko, V., Samigulin, M., Ioilev, A., Lo, S., Tentner, A., Lychagin, A., Razin, A., Girin, V., Vanyukov, Ye., Nuclear Engineering Division, Russian Russian Federation, & CD-adapco. Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.. United States.
Ustinenko, V., Samigulin, M., Ioilev, A., Lo, S., Tentner, A., Lychagin, A., Razin, A., Girin, V., Vanyukov, Ye., Nuclear Engineering Division, Russian Russian Federation, and CD-adapco. Mon . "Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.". United States. doi:.
@article{osti_944030,
title = {Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.},
author = {Ustinenko, V. and Samigulin, M. and Ioilev, A. and Lo, S. and Tentner, A. and Lychagin, A. and Razin, A. and Girin, V. and Vanyukov, Ye. and Nuclear Engineering Division and Russian Russian Federation and CD-adapco},
abstractNote = {To allow the detailed analysis of the two-phase coolant flow and heat transfer phenomena in a boiling water reactor fuel bundle the CFD-BWR model is being developed for use with the commercial code STAR-CD which provides general two-phase flow modeling capabilities. The paper reviews the key boiling phenomenological models, describes the overall strategy adopted for the combined CFD-BWR and STAR-CD boiling models validation and presents results of a set of experiment analyses focused on the validation of specific models implemented in the code. The location of vapor generation onset, axial temperature profile and axial and radial void distributions were calculated and compared with experimental data. Good agreement between computed and measured results was obtained for a large number of test cases.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}

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  • No abstract prepared.
  • This paper presents recent results obtained as part of the on-going integral validation of an advanced Eulerian-Eulerian two-phase (E2P) computational fluid dynamics based boiling model that allows the detailed analysis of the two-phase flow and heat transfer phenomena in a Boiling Water Reactor (BWR) fuel assembly. The code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities. Simulations of a prototypic BWR fuel assembly experiment have been completed as an initial assessment of the applicability of the E2P model to realistic BWR geometries and conditions. Initialmore » validation has focused on comparison with measured sub-channel averaged data to enable the benchmarking of the accuracy of the E2P against the current predictive capabilities of the sub-channel methods. The paper will discuss the effects of modeling assumptions, assumed coefficient values and the computational mesh structure used to describe the fuel assembly geometry on the accuracy of the sub-channel averaged void fraction.« less
  • No abstract prepared.
  • A new code, CFD-BWR, is being developed for the simulation of two-phase flow phenomena inside a BWR fuel bundle. These phenomena include coolant phase changes and multiple flow regimes which directly influence the coolant interaction with fuel assembly and, ultimately, the reactor performance. CFD-BWR is a specialized module built on the foundation of the commercial CFD code STAR-CD which provides general two-phase flow modeling capabilities. New models describing the inter-phase mass, momentum, and energy transfer phenomena specific for BWRs have been developed and implemented in the CFD-BWR module. A set of experiments focused on two-phase flow and phase-change phenomena hasmore » been identified for the validation of the CFD-BWR code and results of two experiment analyses focused on the radial void distribution are presented. The close agreement between the computed results, the measured data and the correlation results provides confidence in the accuracy of the models. (authors)« less