Experimental and numerical analysis of single pump failure in a HLM reactor

Philippe Planquart; Katrien Van Tichelen

doi:10.13182/T123-33067

Experimental and numerical analysis of single pump failure in a HLM reactor

Philippe Planquart
, Katrien Van Tichelen

Research output › peer-review

Abstract

Water modeling of the primary circuit of a new reactor provides useful information on the thermal-hydraulics of the reactors and provides quantitative data for validation of numerical simulation. The accidental scenario of a single
pump failure in a pool type reactor driven by two pumps is characterized by different thermal zones in the upper plenum [1] which makes this case particular interesting for the validation of CFD. Results of validation of this transient
test case are presented showing a good comparison between CFD and measurements. Additional work is currently performed on the uncertainty quantification of both the numerical and experimental approaches.

Original language	English
Title of host publication	Transactions
Publisher	American Nuclear Society
Pages	1523-1524
Number of pages	2
Volume	123
Edition	1
DOIs	https://doi.org/10.13182/T123-33067
State	Published - Nov 2020
Event	2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020 - Virtual, Online Duration: 16 Nov 2020 → 20 Nov 2020

Publication series

Name	Transactions of the American Nuclear Society
Publisher	American Nuclear Society
ISSN (Print)	0003-018X

Conference

Conference	2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020
Country/Territory	United States
City	Virtual, Online
Period	2020-11-16 → 2020-11-20

ASJC Scopus subject areas

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality

Access to Document

10.13182/T123-33067

Cite this

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title = "Experimental and numerical analysis of single pump failure in a HLM reactor",

abstract = "Water modeling of the primary circuit of a new reactor provides useful information on the thermal-hydraulics of the reactors and provides quantitative data for validation of numerical simulation. The accidental scenario of a single pump failure in a pool type reactor driven by two pumps is characterized by different thermal zones in the upper plenum [1] which makes this case particular interesting for the validation of CFD. Results of validation of this transient test case are presented showing a good comparison between CFD and measurements. Additional work is currently performed on the uncertainty quantification of both the numerical and experimental approaches.",

keywords = "CFD, Measurement, HLM reactor",

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Planquart, P & Van Tichelen, K 2020, Experimental and numerical analysis of single pump failure in a HLM reactor. in Transactions. 1 edn, vol. 123, Transactions of the American Nuclear Society, American Nuclear Society, pp. 1523-1524, 2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020, Virtual, Online, United States, 2020-11-16. https://doi.org/10.13182/T123-33067

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AB - Water modeling of the primary circuit of a new reactor provides useful information on the thermal-hydraulics of the reactors and provides quantitative data for validation of numerical simulation. The accidental scenario of a single pump failure in a pool type reactor driven by two pumps is characterized by different thermal zones in the upper plenum [1] which makes this case particular interesting for the validation of CFD. Results of validation of this transient test case are presented showing a good comparison between CFD and measurements. Additional work is currently performed on the uncertainty quantification of both the numerical and experimental approaches.

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