Stratification of entrapped sodium as insulation in an LMFBR pool-type reactor vessel
Description
The use of thermal stratification of a trapped layer of sodium is demonstrated as an effective method of insulating the thermal-hydraulic separator between the hot and cold pools in a pool-type reactor vessel for a liquid metal fast breeder reactor (LMFBR). Using the VARR-II computer program, a 2-D thermal-hydraulic analysis of the critical cross section of the fluid layer predicts a smoothly changing thermal stratification resulting in the separator exeriencing 11% of the temperature difference between the pools. Vertical nonadiabatic penetrations of the soidum layer create localized natural convection currents which are not found to significantly disrupt the thermal stratification. Several geometric and thermal boundary condition variations are also inspected
Additional details
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods
- Journal Page Range
- p. 1882-1895.
- Report number
- NUREG/CP--0014(Vol.3)
Conference
- Title
- ANS/ASME topical meeting on reactor thermal-hydraulics.
- Dates
- 9 - 12 Oct 1980.
- Place
- Saratoga, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12642330
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR COMPONENTS; REACTOR VESSELS; SODIUM; SPATIAL DISTRIBUTION; STRATIFICATION
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; CONTAINERS; DISTRIBUTION; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTORS