Analytical criteria for fuel failure modes observed in reactivity initiated accidents
Description
The behaviour of nuclear fuel subjected to a short duration power pulse is of relevance to LWR and CANDU reactor safety. A Reactivity Initiated Accident (RIA) in an LWR would subject fuel to a short duration power pulse of large amplitude, whereas in CANDU a large break Loss of Coolant Accident (LOCA) would subject fuel to a longer duration, lower amplitude power excursion. The energy generated in the fuel during the power pulse is a key parameter governing the fuel response. This paper reviews the various power pulse tests that have been conducted in research reactors over the past three decades and summarizes the fuel failure modes that that have been observed in these tests. A simple analytical model is developed to characterize fuel behaviour under power pulse conditions and the model is applied to assess the experimental data from the power pulse tests. It is shown that the simple model provides a good basis for establishing criteria that demarcate the observed fuel failure modes for the various fuel designs that have been used in these tests. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-82-8
- Imprint Title
- 26th Annual CNS conference; 29th CNS/CNA student conference
- Imprint Pagination
- 168 Megabytes
- Journal Page Range
- [17 p.]
Conference
- Title
- 26. Annual CNS conference; 29. CNS/CNA student conference. Proceedings
- Dates
- 12-15 Jun 2005
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 38042018
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL ELEMENT FAILURE; LOSS OF COOLANT; REACTOR ACCIDENTS; REACTOR SAFETY; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; FAILURES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS
Optional Information
- Notes
- 29 refs., 1 tab., 6 figs.