The Potential for Fuel-Target Mixing during a Fuel Melting Accident in the SRS Fuel Assembly

Conference · Sun Sep 30 04:00:00 EDT 1990

OSTI ID:6116102

Epstein, M. ^[1]; Ellison, P. G. ^[2]; Paik, I. K. ^[2]; Coryell, E. W. ^[3]

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1. Fauske & Associates, LLC, Burr Ridge, IL (United States)
2. Westinghouse Savannah River Co., Savannah River Site (SRS), Aiken, SC (United States)
3. EG and G Idaho, Inc., Idaho Falls, ID (United States)

The mechanical work potential during a whole core melting accident in the Savannah River Site production reactors is strongly influenced by the amount of target material mixing with the fuel. This strong fluence on accident progression is the result of the potential for recriticality of the fuel and the possibility of steam explosions with the molten fuel-target material. In this paper an analysis of the temperature and draining history of the fuel film/target wall composite is made on the basis of conduction theory. The formulation includes the effects of turbulent fuel-film flow and finite target wall/fuel-film geometry. The computational procedure results in predictions of the fraction of the deposited fuel that is likely to mix with the substrate material as a function of target wall thickness and length of the fuel deposit.

• Research Organization: Fauske & Associates, LLC, Burr Ridge, IL (United States); Westinghouse Savannah River Co., Savannah River Site (SRS), Aiken, SC (United States); EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 6116102
• Report Number(s): WSRC-MS-90-20; CONF-900917--37; ON: DE91009340
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CORIUM
DEPOSITION
DROPLETS
ENERGY TRANSFER
ENTHALPY
FLUID MECHANICS
FUEL ASSEMBLIES
FUSION HEAT
Fuel-Film Flow
Fuel-Melt Film
GEOMETRY
HEAT TRANSFER
HYDRAULICS
High Thermal Conductivity
IRRADIATION
MATHEMATICAL MODELS
MATHEMATICS
MECHANICS
MELTDOWN
MELTING
MIXING
Molten Fuel Film
NATIONAL ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
ONE-DIMENSIONAL CALCULATIONS
PARTICLES
PHASE TRANSFORMATIONS
PHYSICAL PROPERTIES
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
SAVANNAH RIVER PLANT
SOLIDIFICATION
SPECIAL PRODUCTION REACTORS
SPECIFIC HEAT
TARGETS
TEMPERATURE DEPENDENCE
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSITION HEAT
Target Wall
US AEC
US DOE
US ERDA
US ORGANIZATIONS
Whole Core Melting Accident