Post accident heat transfer of relocated fuel on the grid plate in a metal-fuelled FBR
- 1. Reactor Design Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
Metal-fuelled fast reactor with U-Pu-Zr ternary alloy as fuel are now being considered with renewed research interest because of its high breeding gain and low doubling time. A Metal Fuelled Test Reactor is being designed at IGCAR. As part of safety analysis, transient thermal response of the grid plate to the decay heat generating molten fuel settling above it is studied by heat transfer computations. A whole core melt-down is assumed. Numerical analysis is done using in-house HEATRAN-1 code to obtain the temperature evolution in the grid plate. The paper summarizes the results obtained for a few possible configurations of core-melt on the grid plate by varying the extent of core-melt spreading on the grid plate and the boundary conditions as parameters. The results indicate that grid plate melt-through can happen in the worst case of whole core-melt settling upon the grid plate in the lumped form. (author)
Additional details
Publishing Information
- Publisher
- Indian Space Research Organisation
- Imprint Place
- Trivandrum (India)
- Imprint Title
- Proceedings of the twenty third national heat and mass transfer conference and first international ISHMT-ASTFE heat and mass transfer conference: souvenir and book of abstracts
- Imprint Pagination
- 269 p.
- Journal Page Range
- p. 175
Conference
- Title
- 23. national heat and mass transfer conference; ISHMT-ASTFE: international heat and mass transfer conference
- Acronym
- IHMTC-2015
- Dates
- 17-20 Dec 2015
- Place
- Trivandrum (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 48043249
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; KALPAKKAM PFBR REACTOR; MELTDOWN; PLUTONIUM; REACTOR CORES; SAFETY ANALYSIS; URANIUM
- Descriptors DEC
- ACCIDENTS; ACTINIDES; BREEDER REACTORS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; METALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TRANSURANIUM ELEMENTS