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--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
- Country of Publication:
- United States
- Language:
- English
Similar Records
Post-test analysis of the BTF-104 severe-fuel-damage experiment using the CATHENA thermal-hydraulics code
Tritium activities in Canada
Radioactive waste management in Canada - Science, strategy, and outlook
Book
·
Mon Jul 01 00:00:00 EDT 1996
·
OSTI ID:250989
Tritium activities in Canada
Journal Article
·
Thu Jun 01 00:00:00 EDT 1995
· Journal of Fusion Energy
·
OSTI ID:263646
Radioactive waste management in Canada - Science, strategy, and outlook
Conference
·
Sun Dec 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6808867
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CANDU TYPE REACTORS
DAMAGE
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HEAVY WATER MODERATED REACTORS
PRESSURE TUBE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTORS
RESEARCH PROGRAMS
TESTING
THERMAL REACTORS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CANDU TYPE REACTORS
DAMAGE
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HEAVY WATER MODERATED REACTORS
PRESSURE TUBE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTORS
RESEARCH PROGRAMS
TESTING
THERMAL REACTORS