TRANSIT-HYDRO transition phase accident analysis code: an overview and recent improvements

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5705595

Wigeland, R A; Briggs, L L

The TRANSIT-HYDRO computer code is being developed to provide a tool for assessing the consequences of transition phase events in a hypothetical core disruptive accident in an LMFBR. The TRANSIT-HYDRO code incorporates detailed geometric modeling on a subassembly-by-subassembly basis and detailed modeling of reactor material behavior and thermal and hydrodynamic phenomena. The purpose of this summary is to give a brief overview of the code and to describe recent improvements to the code, particularly the addition of new phenomenological models. Sample results with these new models are also described. The TRANSIT-HYDRO code is constructed on a modular basis, which allows models to be added or changed readily. In this summary, the emphasis is on the disrupted subassembly module which is used once the fuel pin inside the subassembly starts to disrupt.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5705595
• Report Number(s): CONF-850410-24; ON: DE85005043
• Country of Publication: United States
• Language: English

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
BREEDER REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRODYNAMICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION