Source Term Calculations for Loss of Cooling Accident at CANDU Spent Fuel Pool
Description
An investigation of the loss of cooling accident at a CANDU type spent fuel pool is presented. The analysis is intended to understand the potential of the accident to evolve towards a severe accident. The daily refuelling together with the relatively low burnup of the CANDU fuel ensure a large grace time for the intervention (around 2 weeks). Adding make-up water at a flow rate of 1.25 kg/s is sufficient to keep a constant level of water in the pool. However, in case of the refurbishment process (replacement of fuel channels to extend the plant life) a full core is discharged. The potential of a loss of cooling accident to evolve towards a severe accident was detailed investigated by numerical simulation using some of the modules of the ASTEC code. The main results consist of the transfer fraction for the most important elements of the source term. (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. 151-164
- 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
- 52040759
- 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
- BURNUP; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; FLOW RATE; FUEL CHANNELS; FUEL STORAGE POOLS; SEVERE ACCIDENTS; SOURCE TERMS; SPENT FUELS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- 17 refs., 7 figs., 2 tabs.