Recriticality risk in PWR spent fuel pools
- 1. Institut National des Sciences et Techniques, NuclÃl'aires, Ecole Nationale SupÃl'irieure des Mines de Nancy (France)
- 2. University of Fukui, Research Institute of Nuclear Engineering, Tsuruga, Fukui (Japan)
Description
In this paper we investigated the situation in a PWR Spent Fuel Pool (SFP) following a long-term loss of power / loss of cooling accident. In the SFP there is a large amount of water with soluble boron between the fuel assemblies. There may be a problem from the point of view of criticality safety if the water of the SFP starts to boil and evaporate. A thermal-hydraulic analysis was performed using a simplified model of the SFP. The thermal-hydraulic analysis shows that in all cases a chaotic boiling phenomenon develops. This indicates that even if there is an issue of (near-)criticality, it will have a very intermittent nature. The multiplication factor of the SFP was evaluated with a Monte Carlo calculation. The neutronic analysis was performed for several representative cooling situations. In all cases, the system remains (deeply) subcritical. (author)
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 16 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042536
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; CRITICALITY; FUEL ASSEMBLIES; FUEL RACKS; FUEL STORAGE POOLS; LOSS OF COOLANT; M CODES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NATURAL CONVECTION; PWR TYPE REACTORS; R CODES; RISK ASSESSMENT; SPENT FUEL STORAGE; SPENT FUELS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; CONVECTION; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUELS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MATERIALS; MECHANICAL STRUCTURES; MECHANICS; NUCLEAR FUELS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; STORAGE; SUPPORTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1081521.pdf; 4 refs., 13 figs., 8 tabs.