Fuel pin failure in the PFR/TREAT experiments
Conference
·
OSTI ID:5547379
The PFR/TREAT safety testing programme involves the transient testing of fresh and pre-irradiated UK and US fuel pins. This paper summarizes the experimental and calculational results obtained to date on fuel pin failure during transient overpower (resulting from an accidental addition of resolivity) and transient undercooling followed by overpower (arising from an accidental stoppage of the primary sodium circulating pumps) accidents. Companion papers at this conference address: (I) the progress and future plans of the programme, and (II) post-failure material movements.
- Research Organization:
- Argonne National Lab., IL (USA); Hanford Engineering Development Lab., Richland, WA (USA); UKAEA Atomic Energy Establishment, Winfrith. Safety and Engineering Science Div.
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5547379
- Report Number(s):
- CONF-860501-12; ON: DE86012123
- Country of Publication:
- United States
- Language:
- English
Similar Records
Progress and future plans in the PFR/TREAT safety testing programs
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Tue Dec 31 23:00:00 EST 1985
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OSTI ID:5507664
PFR/TREAT CO1 and LO1 experiments
Conference
·
Thu Dec 31 23:00:00 EST 1981
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OSTI ID:6342483
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·
OSTI ID:6188112
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
PFR REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
TREAT REACTOR
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
PFR REACTOR
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
TRANSIENT OVERPOWER ACCIDENTS
TREAT REACTOR