Fuel behavior and fission product release in the BTF-107 severe-fuel-damage experiment
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6844062
- Atomic Energy of Canada Ltd., Manitoba (Canada)
The principal experimental tool in Canada for performing in-reactor fuel safety experiments is the Blowdown Test Facility (BTF) located in the national research universal reactor at Atomic Energy of Canada Limited's (AECL's) Chalk River Laboratories. The in-reactor experiments performed in the BTF are designed to obtain data on the behavior of Canada deuterium uranium (CANDU) fuel under accident conditions and are currently funded by the CANDU Owners Group, a cost-sharing partnership between AECL and the Canadian electrical utilities that own CANDU pressurized heavy-water reactors (Ontario Hydro, Hydro-Quebec, and New Brunswick Power).
- OSTI ID:
- 6844062
- Report Number(s):
- CONF-931160-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 69; Conference: American Nuclear Society (ANS) winter meeting, San Francisco, CA (United States), 14-18 Nov 1993; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CANDU TYPE REACTORS
FUEL ELEMENTS
FISSION PRODUCT RELEASE
DAMAGE
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
RESEARCH PROGRAMS
TESTING
ACCIDENTS
HEAVY WATER MODERATED REACTORS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CANDU TYPE REACTORS
FUEL ELEMENTS
FISSION PRODUCT RELEASE
DAMAGE
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
RESEARCH PROGRAMS
TESTING
ACCIDENTS
HEAVY WATER MODERATED REACTORS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated