Code Benchmark of a Depressurized Conduction Cooldown Transient in the High Temperature Test Facility

Robert F. Kile, Aaron S. Epiney, Thanh Hua, Ling Zou, Sung Nam Lee, Geoff Waddington, Xianmin Huang, Tariq Jafri, Fajar Pangukir, Marek Stempniewicz, Ferry Roelofs, Gusztáv Mayer, Zsombor Bali

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

Abstract

We present results from modeling of a depressurized conduction cooldown (DCC) at the High Temperature Test Facility (HTTF) in the OECD-NEA Thermal Hydraulics Code Validation Benchmark for High-Temperature Gas-Cooled Reactors using HTTF Data. We briefly describe the benchmark and the models being used. We then present a comparison of steady state and transient results based on the Problem 2 Exercise 1A and 1B. We compare distributions of block and helium temperatures and coolant flow. We also compare energy balance in steady state. All models show comparable mass flow distributions and energy balances. The temperatures within the core and outer regions are comparable in all models too, but inner reflector temperatures can vary significantly. Despite that, we find that the models are in good agreement for the full-power steady state. In the DCC, we look at block temperature at the core midplane and RCCS water exit temperature. The INL and ANL models are found to be in excellent agreement with one another on block temperature over time, and when the KAERI and NRG models are considered agreement is good. Differences in the transient heat removal from the RCCS cause the differences in block temperature over time. The CNL models show similar trends to the INL, ANL, KAERI, and NRG models, but the temperatures are high because the volumes used in calculating the average temperature include the heater rods in the CNL models. The HUN-REN model shows slightly different RCCS behavior than other models, leading to differences in results, but these differences do not suggest fundamental differences.

Original languageEnglish
Title of host publicationProceedings of Advances in Thermal Hydraulics, ATH 2024
PublisherAmerican Nuclear Society
Pages486-499
Number of pages14
ISBN (Electronic)9780894482205
DOIs
StatePublished - Nov 17 2024
Event2024 Advances in Thermal Hydraulics, ATH 2024 - Orlando, United States
Duration: Nov 17 2024Nov 21 2024

Publication series

NameProceedings of Advances in Thermal Hydraulics, ATH 2024

Conference

Conference2024 Advances in Thermal Hydraulics, ATH 2024
Country/TerritoryUnited States
CityOrlando
Period11/17/2411/21/24

Keywords

  • Benchmark
  • HTGR
  • HTTF
  • code-to-code comparison
  • system code

INL Publication Number

  • INL/MIS-24-81858
  • 189665

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