Published 2005 | Version v1
Miscellaneous

Analytical criteria for fuel failure modes observed in reactivity initiated accidents

Creators

  • 1. McMaster Univ., Dept. of Engineering Physics, Hamilton, Ontario (Canada)

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)

Part of:
26th Annual CNS conference; 29th CNS/CNA student conference

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.