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.
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 |
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Title of host publication | Transactions |
Publisher | American Nuclear Society |
Pages | 1523-1524 |
Number of pages | 2 |
Volume | 123 |
Edition | 1 |
DOIs | |
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 |
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Publisher | American Nuclear Society |
ISSN (Print) | 0003-018X |
Conference
Conference | 2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020 |
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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