Simulation of decay heat removal in high temperature gas-cooled reactors
Description
As one of the next generation nuclear power systems, the Gas Turbine Modular Helium Reactor (GT-MHR) achieves improved safety by relying upon inherent thermal storage characteristics and passive cooling features to maintain fuel and reactor vessel integrity if all its active cooling systems fail to operate in the unlikely event referred to as conduction cooldown. In designing the passive natural draft cooling system for the GT-MHR, computational fluid dynamic (CFD) models have been developed to model the passive heat transfer processes and predict the resultant reactor fuel and component temperatures. To initiate validation of the analytical methods used for this critical safety application, a benchmark heat transfer experiment performed at the Japanese Atomic Energy Research Institute (JAERI), which partially models the in-vessel and ex-vessel decay heat removal heat transfer of the GT-MHR, was simulated using the finite element-based FIDAP CFD analysis package. The steady state model incorporated conjugate heat transfer, diffuse grey-body surface radiation, and a Boussinesq model for buoyancy driven convection. Since Rayleigh numbers for the experiment ranged from 106 to 107 inside the vessel and from 108 to 109 outside the vessel, both laminar and turbulent flow models were evaluated. The analysis results show good agreement with the experiment test data
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1751-2
- Imprint Title
- Proceedings of the ASME Heat Transfer Division. Volume 1: Benchmark problems of heat transfer analysis programs; High heat flux thermal management; Modeling of heat transfer in multi-phase systems; Natural and mixed convection; Numerical methods in heat exchanger design; HTD-Volume 317-1
- Imprint Pagination
- 484 p.
- Journal Page Range
- p. 331-339.
Conference
- Title
- 1995 International mechanical engineering congress and exhibition.
- Dates
- 12-17 Nov 1995.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28045664
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; GAS COOLED REACTORS; NATURAL CONVECTION; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; HEAT TRANSFER; REACTORS; REMOVAL
Optional Information
- Contract/Grant/Project number
- Contract AC03-89SF17887
- Secondary number(s)
- CONF-951135--.