Molten core debris-sodium interactions: M-Series experiments. [LMFBR]
Conference
·
OSTI ID:5779342
Five new kilogram-scale experiments have been carried out. Four of the experiments simulated the situation where molten core debris flows from a breached reactor vessel into a dry reactor cavity and is followed by a flow of sodium (Ex-vessel case) and one experiment simulated the flow of core debris into an existing pool of sodium (In-vessel case). The core debris was closely simulated by a thermite reaction which produced a molten mixture of UO/sub 2/, ZrO/sub 2/, and stainless steel. There was efficient fragmentation of the debris in all experiments with no explosive interactions observed.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5779342
- Report Number(s):
- CONF-790816-59; TRN: 79-022198
- Resource Relation:
- Conference: International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of materials for retention of sodium and core debris in reactor systems. Annual progress report, September 1977-December 1978. [LMFBR]
Effects of lateral separation of oxidic and metallic core debris on the BWR MK I containment drywell floor
Effects of lateral separation of oxidic and metallic core debris on the BWR MK I containment drywell floor
Technical Report
·
Fri Dec 01 00:00:00 EST 1978
·
OSTI ID:5779342
+2 more
Effects of lateral separation of oxidic and metallic core debris on the BWR MK I containment drywell floor
Conference
·
Wed Jan 01 00:00:00 EST 1986
·
OSTI ID:5779342
Effects of lateral separation of oxidic and metallic core debris on the BWR MK I containment drywell floor
Conference
·
Wed Jan 01 00:00:00 EST 1986
·
OSTI ID:5779342
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL-COOLANT INTERACTIONS
REACTION KINETICS
LMFBR TYPE REACTORS
MELTDOWN
CORIUM
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
KINETICS
LIQUID METAL COOLED REACTORS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding