The postirradiation examination of the DC (Dry Capsule) melt dynamics experiments
Technical Report
·
OSTI ID:7131777
The Dry Capsule experiment series investigates the coolability of dry fast reactor core debris through nuclear heating of actual reactor materials in order to obtain the thermal properties of dry debris, the nature of the transition from a debris bed to a molten pool, and the thermal and kinetic behavior of molten pools. The purpose is to develop a data base in support of model development. The work is jointly sponsored by the US Nuclear Regulatory Commission (USNRC), the Power Reactor and Nuclear Fuel Development Corporation (PNC, Japan), and Joint Research Centre, Ispra (EURATOM). This report provides a brief description of the two experiments in the Dry Capsule series and presents the results of the postirradiation examination. These tests investigated dry debris beds (/approximately/2kg) composed of pure UO/sub 2/ and mixed UO/sub 2/ and stainless steel. The beds were taken into melt to observe the growth of a molten pool in the UO/sub 2/ bed and the agglomeration and migration of steel in a composite bed. The peak measured temperature in the UO/sub 2/ bed was above 3100/degree/C. Approximately 50 percent of the urania formed a molten pool. Surrounding the molten pool and an overlying void was a high density urania crust. Lenticular pore formation and migration caused by urania vapor transport in the strong thermal gradient were seen in the urania crust. In the mixed UO/sub 2/ and steel bed, the peak measured temperature was 2600/degree/ C. All of the steel had been molten. Steel and urania migration were observed; both were thought to be caused by vapor transport mechanisms.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Accident Analysis; Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7131777
- Report Number(s):
- NUREG/CR-4625; SAND-86-1102; ON: TI88014785
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CORIUM
CORROSION RESISTANT ALLOYS
DATA
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
GASES
HEAT TRANSFER
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION CAPSULES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MELTING
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
POST-IRRADIATION EXAMINATION
REACTOR MATERIALS
REACTORS
RESEARCH PROGRAMS
STAINLESS STEELS
STEELS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
VAPORS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHROMIUM ALLOYS
CORIUM
CORROSION RESISTANT ALLOYS
DATA
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
GASES
HEAT TRANSFER
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION CAPSULES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MELTING
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
POST-IRRADIATION EXAMINATION
REACTOR MATERIALS
REACTORS
RESEARCH PROGRAMS
STAINLESS STEELS
STEELS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
VAPORS