TRANS4: a computer code calculation of solid fuel penetration of a concrete barrier. [LMFBR; GCFR]
The computer code, TRANS4, models the melting and penetration of a solid barrier by a solid disc of fuel following a core disruptive accident. This computer code has been used to model fuel debris penetration of basalt, limestone concrete, basaltic concrete, and magnetite concrete. Sensitivity studies were performed to assess the importance of various properties on the rate of penetration. Comparisons were made with results from the GROWS II code.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6808169
- Report Number(s):
- ANL-80-63; TRN: 81-000939
- 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
COMPUTER CODES
T CODES
GCFR TYPE REACTORS
REACTOR CORE DISRUPTION
LMFBR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
ABLATION
CONCRETES
CONTAINMENT BUILDINGS
CORE CATCHERS
CORIUM
FAILURES
MELTDOWN
NATURAL CONVECTION
REACTOR SAFETY
THERMAL STRESSES
ACCIDENTS
BREEDER REACTORS
BUILDING MATERIALS
CONTAINMENT
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
GAS COOLED REACTORS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
T CODES
GCFR TYPE REACTORS
REACTOR CORE DISRUPTION
LMFBR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
ABLATION
CONCRETES
CONTAINMENT BUILDINGS
CORE CATCHERS
CORIUM
FAILURES
MELTDOWN
NATURAL CONVECTION
REACTOR SAFETY
THERMAL STRESSES
ACCIDENTS
BREEDER REACTORS
BUILDING MATERIALS
CONTAINMENT
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
GAS COOLED REACTORS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding