Silver-indium-cadmium control rod behavior in severe reactor accidents
Journal Article
·
· Nuclear Technology; (USA)
OSTI ID:5740107
- Idaho National Engineering Lab., Idaho Falls, ID (USA)
Silver-indium-cadmium (Ag-In-Cd) control rod behavior in severe reactor accidents is examined with a goal of improving the methodology used to estimate reactor accident source terms. Control rod behavior in both in-pile and out-of-pile experiments is reviewed. A mechanistic model named VAPOR is developed that calculates the downward relocation and simultaneous vaporization behavior of the Ag-In-Cd alloy expected after control rod failure in a severe reactor accident. VAPOR is used to predict the release of silver, indium, and cadmium vapors expected in the Power Burst Facility (PBF) severe fuel damage (SFD) 1-4 experiment. In addition, a sensitivity study is performed to examine the effects of system pressure and flow rate on control rod vapor release. Although cadmium is found to be the most volatile constituent of the alloy, all of the calculations predict that the rapid relocation of the alloy down to cooler portions of the core results in a limited release for all three control rod alloy vapors. Results of the control rod and aerosol behavior in PBF and SFD 1-4 are presented.
- OSTI ID:
- 5740107
- Journal Information:
- Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 84:2; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
CADMIUM
CALCULATION METHODS
COLLOIDS
CONTROL ROD DRIVES
DISPERSIONS
ELEMENTS
FISSION PRODUCTS
FLUIDS
FUEL-CLADDING INTERACTIONS
GASES
INDIUM
ISOTOPES
MATERIALS
METALS
POLLUTION SOURCES
RADIOACTIVE AEROSOLS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
SILVER
SOLS
TEST FACILITIES
TRANSITION ELEMENTS
VAPORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
CADMIUM
CALCULATION METHODS
COLLOIDS
CONTROL ROD DRIVES
DISPERSIONS
ELEMENTS
FISSION PRODUCTS
FLUIDS
FUEL-CLADDING INTERACTIONS
GASES
INDIUM
ISOTOPES
MATERIALS
METALS
POLLUTION SOURCES
RADIOACTIVE AEROSOLS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
SILVER
SOLS
TEST FACILITIES
TRANSITION ELEMENTS
VAPORS