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

Conference ·
OSTI ID:2484285
 [1];  [2];  [2];  [3];  [4];  [4];  [4];  [5];  [5];  [5];  [6];  [7];  [1]
  1. Idaho National Laboratory
  2. Argonne National Laboratory
  3. Korea Atomic Energy Research Institue
  4. Canadian Nuclear Laboratories
  5. Nuclear Research and Consultancy Group
  6. HUN-REN Centre for Energy Research; Budapest University of Technology and Economics
  7. HUN-REN Centre for Energy Research

This paper presents results from modeling of a depressurized conduction cooldown (DCC) transient at the High Temperature Test Facility (HTTF) as part of the OECD-NEA Thermal Hydraulics Code Validation Benchmark for High-Temperature Gas-Cooled Reactors using HTTF Data . This paper briefly describes the benchmark and the models being used. It then presents a comparison of steady state and transient results based on the Problem 2 Exercise 1A and 1B definitions. We compare block and helium temperature distributions, mass flow distribution, and 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, while the agreement when the KAERI and NRG models are added into consideration is good. Differences in the transient heat removal from the RCCS cause the differences in block temperature over time in these models. 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 only. The HUN-REN model shows results that suggest significantly lower heat removal in the RCCS which merit further investigation.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
58
DOE Contract Number:
AC07-05ID14517
OSTI ID:
2484285
Report Number(s):
INL/CON-24-78260-Rev000
Country of Publication:
United States
Language:
English

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