Simulation of CANDU Fuel Thermal-Hydraulic Behaviour During Spent Fuel Bay Loss of Cooling Events
Description
After the Fukushima accident, one of the highest priorities for CERNAVODA NPP was to investigate events that can lead to Spent Fuel Bay (SFB) loss of cooling and loss of coolant inventory. In CANDU plants, fuelling is performed on-power. Daily, fresh fuel bundles are loaded in core and spent fuel bundles are discharged from the core, transferred and stored in SFB. Due to the SFB limited storage capacity, bundles having 6 years or more of cooling time are transferred to the Dry Storage Facility. Thus, as per design, a maximum number of around 38 000 fuel bundles can be stored, at any time, in SFB. Following a loss of class III and class IV power sources (e.g. Station Blackout), the cooling and purification systems for SFB water become unavailable. Consequently, the bay water temperature increases up to the boiling conditions and, due to boiling and vaporization, the water inventory and level will decrease in time. The decrease of coolant level can leave uncovered a number of fuel bundles, degrading their cooling. The present paper reviews the analysis methodology and results for a typical event of Spent Fuel Bay loss of cooling. Methodologies used in the analysis and results presented are focused upon the CANDU fuel thermal-hydraulic behaviour during the event and upon its potential radiological hazard. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-104121-0
- Imprint Title
- Phenomenology, Simulation and Modelling of Accidents in Spent Fuel Pools. Proceedings of a Technical Meeting
- Imprint Pagination
- 266 p.
- Journal Page Range
- p. 165-181
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1949
Conference
- Title
- Technical Meeting on the Phenomenology, Simulation and Modelling of Accidents in Spent Fuel Pools
- Dates
- 2-5 Sep 2019
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52040760
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; COOLANTS; DRY STORAGE; FUEL COOLING TIME; FUEL ELEMENT CLUSTERS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; RADIATION HAZARDS; REACTOR DESIGN; SPENT FUELS; STATION BLACKOUT; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; COOLING TIME; DESIGN; ENERGY SOURCES; FLUID MECHANICS; FUEL ASSEMBLIES; FUELS; HAZARDS; HEALTH HAZARDS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MATERIALS; MECHANICS; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SIMULATION; STORAGE; THERMAL POWER PLANTS; THERMAL REACTORS
Optional Information
- Notes
- 16 refs., 9 figs., 1 tab.