Natural convection in rectangular pool with volumetric heat sources
Creators
- 1. Seoul National University, Seoul (Korea, Republic of)
Description
Natural convection plays an important role in determining the thermal load from debris accumulated in the reactor vessel lower head during a severe accident. Recently attentions are being paid to the feasibility of external vessel flooding as a severe accident management, and to the phenomena affecting the success path in retaining the molten core material inside the vessel. The heat transfer within the molten core material can be characterized by buoyancy-induced flows resulting from internal heating due to decay of fission products. The thermo-fluid dynamic characteristics of the molten pool depend strongly on the thermal boundary conditions. The spatial and temporal variation of heat flux on the pool wall boundaries and the pool superheat are mainly characterized by the natural convection flow inside the molten pool. In general, natural convection involving internal heat generation is delineated in terms of the modified Rayleigh number, Ra', which quantifies the internal heat source and hence the strength of buoyancy. The test section is of rectangular cavity whose length, width, and height are 500mm, 80mm, and 250mm, respectively. A total of twenty-four T-type thermocouples were installed in the test loop to measure temperature distribution. Four T-type thermocouples were utilized to measure temperatures on the boundary. A direct heating method was adopted in this test to simulate the uniform heat generation. The experiments covered a range of Rayleigh number, Ra, between 4.87x107 and 2.32x1014 and Prandtl number, Pr, between 0.7 and 3.98. Tests were conducted with water and air as simulant. The upper and lower boundary conditions were maintained at a uniform temperature of 10 .deg. C
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [11 p.]
Conference
- Title
- 2003 spring meeting of the KNS
- Dates
- 29-30 May 2003
- Place
- Gyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 35063916
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FEASIBILITY STUDIES; HEAT FLUX; HEAT SOURCES; HEAT TRANSFER; LOSS OF COOLANT; NATURAL CONVECTION; PRANDTL NUMBER; REACTOR CORES; REACTOR VESSELS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS
Optional Information
- Notes
- 15 refs, 6 figs, 1 tab