A Study on Thermal Performance using Conjugated Heat Transfer Analysis for the OASIS-32D Spent Nuclear Fuel Cask
- 1. KEPCO E and C, Daejeon (Korea, Republic of)
Description
A numerical analysis has been performed considering a conjugate heat transfer which includes conduction, radiation, and natural convection. To evaluate PCT and conjugated heat transfer phenomena, the CFD has been performed considering Effective Thermal Conductivity (ETC) of fuel assemblies. Also, and temperature distribution in the cask structure are calculated. The OASIS-32D is a spent nuclear fuel transportation and storage cask developed by KEPCO-E and C. There is no significant fluid temperature of realizable k- ε and k- w SST turbulence model. The temperature profile of position for material is similar. Therefore the CFD simulation for SNF cask is unaffected by turbulence model. The temperature distribution of cask is asymmetry by reason of buoyancy and the geometry effect of fluid region area between basket and fuel bundles. The maximum temperature of fuel bundles is 327.5 .deg. C that its temperature does not exceed 400 .deg. C. Also allowable operating temperature of internal materials was satisfied during normal conditions. In the future, accident analyses considering fire condition for SNF cask will be carried out.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [4 p.]
Conference
- Title
- 2017 Fall Meeting of the KNS
- Dates
- 25-27 Oct 2017
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49078885
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID MECHANICS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; NUMERICAL ANALYSIS; PERFORMANCE; PWR TYPE REACTORS; SPENT FUEL CASKS; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTIVITY; WASTE STORAGE
- Descriptors DEC
- CASKS; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; MANAGEMENT; MATHEMATICS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; SIMULATION; STORAGE; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 5 figs