A knowledge gap analysis for transient CHF prediction within RELAP5-3D

Meehan, Nicholas A.; Folsom, Charles P.; Brown, Nicholas R.

doi:10.1016/j.nucengdes.2024.113171

Title: A knowledge gap analysis for transient CHF prediction within RELAP5-3D

Journal Article · 29 March 2024 · Nuclear Engineering and Design

DOI: https://doi.org/10.1016/j.nucengdes.2024.113171 · OSTI ID:2426947

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Univ. of Tennessee, Knoxville, TN (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Here we compare several experimental pool and flow boiling critical heat flux experiments with corresponding computational models developed with RELAP5-3D. Encompassed within this paper are several sensitivity analyses for the boiling heat transfer correlations, critical heat flux (CHF) prediction within RELAP5-3D and the thermal properties of the cladding for experiments in the Transient Reactor Test Loop (TRTL) and Transient Reactor Test (TREAT) facilities. The sensitivity analyses were consistent in determining that there is a large contribution from the critical heat flux multiplier which in this application, accounts for the effects of power transient critical heat flux. Comparison to experimental results of both the TREAT CHF-SERTTA experimental campaign and a University of New Mexico (UNM) pool boiling experimental campaign demonstrate both the under-prediction of transient CHF and nucleate boiling heat transfer. To address the gaps in knowledge regarding the transient heating effect for both boiling heat transfer and CHF prediction, we present an experimental test matrix for the TRTL facility that will isolate the power transient effect under PWR relevant operational conditions. The test matrix will incorporate 6 power pulses with a constant energy deposition and a timescale that spans over several orders of magnitude, including a steady state test with an exponential period of 10 s.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC07-05ID14517; NE0009213

OSTI ID:: 2426947

Report Number(s):: INL/JOU-24-79451-Rev000

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: - Vol. 422; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Title: A knowledge gap analysis for transient CHF prediction within RELAP5-3D

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