Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D

Jacob P. Gorton; Nicholas R. Brown; Soon Kyu Lee; Youho Lee

Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D

Jacob P. Gorton, Nicholas R. Brown, Soon Kyu Lee, Youho Lee

Research output: Contribution to conference › Paper › peer-review

Abstract

We present the results of a preliminary comparison of low-pressure transient critical heat flux (CHF) tests conducted in a closed tube test section and best-estimate simulation results. We compare low-pressure experimental CHF test results for stainless steel 316 (SS316) and Inconel 600 test sections to results predicted by models developed in two widely-used thermal hydraulics codes; the system code RELAP5-3D and the Consortium for Advanced Simulation of LWRs (CASL) version of CTF. The objective of the comparison was to determine how well the models would predict CHF and post-CHF tube temperatures and rewetting behavior. The RELAP5-3D and CTF models conservatively predicted the heat flux at which CHF was exceeded for the SS316 models, but both codes showed that CHF was exceeded at a greater heat flux than in the experiment for the Inconel 600 case. RELAP5-3D and CTF overpredicted the post-CHF tube temperature in the SS316 model but underpredicted the Inconel tube temperature, thus demonstrating the need for improved CHF and post-CHF prediction methods for various materials.

Original language	English
Pages	1022-1027
Number of pages	6
State	Published - 2018
Externally published	Yes
Event	International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting - Orlando, United States Duration: Nov 11 2018 → Nov 15 2018

Conference

Conference	International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting
Country/Territory	United States
City	Orlando
Period	11/11/18 → 11/15/18

Funding

This research is in support of Nuclear Energy University Program (NEUP) award #17-12688 and the US Department of Energy Office of Nuclear Energy (DOE-NE) Advanced Fuels Campaign (AFC).

Funders	Funder number
DOE-NE
Office of Nuclear Energy

Keywords

Accident tolerant fuel
Departure from nucleate boiling
Transient critical heat flux

Cite this

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title = "Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D",

abstract = "We present the results of a preliminary comparison of low-pressure transient critical heat flux (CHF) tests conducted in a closed tube test section and best-estimate simulation results. We compare low-pressure experimental CHF test results for stainless steel 316 (SS316) and Inconel 600 test sections to results predicted by models developed in two widely-used thermal hydraulics codes; the system code RELAP5-3D and the Consortium for Advanced Simulation of LWRs (CASL) version of CTF. The objective of the comparison was to determine how well the models would predict CHF and post-CHF tube temperatures and rewetting behavior. The RELAP5-3D and CTF models conservatively predicted the heat flux at which CHF was exceeded for the SS316 models, but both codes showed that CHF was exceeded at a greater heat flux than in the experiment for the Inconel 600 case. RELAP5-3D and CTF overpredicted the post-CHF tube temperature in the SS316 model but underpredicted the Inconel tube temperature, thus demonstrating the need for improved CHF and post-CHF prediction methods for various materials.",

keywords = "Accident tolerant fuel, Departure from nucleate boiling, Transient critical heat flux",

author = "Gorton, {Jacob P.} and Brown, {Nicholas R.} and Lee, {Soon Kyu} and Youho Lee",

note = "Publisher Copyright: {\textcopyright} 2018 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting. All rights reserved.; International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting ; Conference date: 11-11-2018 Through 15-11-2018",

year = "2018",

language = "English",

pages = "1022--1027",

}

Gorton, JP, Brown, NR, Lee, SK & Lee, Y 2018, 'Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D', Paper presented at International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting, Orlando, United States, 11/11/18 - 11/15/18 pp. 1022-1027.

Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D. / Gorton, Jacob P.; Brown, Nicholas R.; Lee, Soon Kyu et al.
2018. 1022-1027 Paper presented at International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting, Orlando, United States.

Research output: Contribution to conference › Paper › peer-review

TY - CONF

T1 - Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D

AU - Gorton, Jacob P.

AU - Brown, Nicholas R.

AU - Lee, Soon Kyu

AU - Lee, Youho

PY - 2018

Y1 - 2018

N2 - We present the results of a preliminary comparison of low-pressure transient critical heat flux (CHF) tests conducted in a closed tube test section and best-estimate simulation results. We compare low-pressure experimental CHF test results for stainless steel 316 (SS316) and Inconel 600 test sections to results predicted by models developed in two widely-used thermal hydraulics codes; the system code RELAP5-3D and the Consortium for Advanced Simulation of LWRs (CASL) version of CTF. The objective of the comparison was to determine how well the models would predict CHF and post-CHF tube temperatures and rewetting behavior. The RELAP5-3D and CTF models conservatively predicted the heat flux at which CHF was exceeded for the SS316 models, but both codes showed that CHF was exceeded at a greater heat flux than in the experiment for the Inconel 600 case. RELAP5-3D and CTF overpredicted the post-CHF tube temperature in the SS316 model but underpredicted the Inconel tube temperature, thus demonstrating the need for improved CHF and post-CHF prediction methods for various materials.

AB - We present the results of a preliminary comparison of low-pressure transient critical heat flux (CHF) tests conducted in a closed tube test section and best-estimate simulation results. We compare low-pressure experimental CHF test results for stainless steel 316 (SS316) and Inconel 600 test sections to results predicted by models developed in two widely-used thermal hydraulics codes; the system code RELAP5-3D and the Consortium for Advanced Simulation of LWRs (CASL) version of CTF. The objective of the comparison was to determine how well the models would predict CHF and post-CHF tube temperatures and rewetting behavior. The RELAP5-3D and CTF models conservatively predicted the heat flux at which CHF was exceeded for the SS316 models, but both codes showed that CHF was exceeded at a greater heat flux than in the experiment for the Inconel 600 case. RELAP5-3D and CTF overpredicted the post-CHF tube temperature in the SS316 model but underpredicted the Inconel tube temperature, thus demonstrating the need for improved CHF and post-CHF prediction methods for various materials.

KW - Accident tolerant fuel

KW - Departure from nucleate boiling

KW - Transient critical heat flux

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M3 - Paper

AN - SCOPUS:85060158555

SP - 1022

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T2 - International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting

Y2 - 11 November 2018 through 15 November 2018

ER -

Comparison of experimental and simulated low-pressure CHF tests using CTF and RELAP5-3D

Abstract

Conference

Funding

Keywords

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