Features of postfailure fuel behavior in transient overpower and transient undercooled/overpower tests in the transient reactor test facility
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:5660208
- Argonne National Lab., Argonne, IL (US)
Prototypic oxide fuel was subjected to simulated, fast reactor severe accident conditions in a series of in-pile tests in the Transient Reactor Test Facility reactor. Seven experiments were performed on fresh and previously irradiated oxide fuel pins under transient overpower and transient undercooled. overpower accident conditions. For each of the tests, fuel motions were observed by the hodoscope. Hodoscope data are correlated with coolant flow, pressure, and temperature data recorded by the loop instrumentation. Data were analyzed from the onset of initial failure to a final mass distribution at the end of the test. In this paper results of these analyses are compared to pre- and posttest accident calculations and to posttest metallographic accident calculations and to posttest metallographic examinations and computed tomographic reconstructions from neutron radiographs.
- OSTI ID:
- 5660208
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 98:1; ISSN 0029-5450; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
TREAT Transient Overpower Tests R9 and R12: Part 2 [Final Report]
TREAT Transient Overpower Tests R9 and R12: Part 1 [Final Report]
Behavior of modern metallic fuel in treat transient overpower tests
Technical Report
·
Mon Mar 31 23:00:00 EST 1980
·
OSTI ID:1130761
TREAT Transient Overpower Tests R9 and R12: Part 1 [Final Report]
Technical Report
·
Mon Mar 31 23:00:00 EST 1980
·
OSTI ID:1130755
Behavior of modern metallic fuel in treat transient overpower tests
Journal Article
·
Fri Nov 30 23:00:00 EST 1990
· Nuclear Technology; (United States)
·
OSTI ID:5080631
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CHALCOGENIDES
COOLANT LOOPS
COOLING SYSTEMS
DATA
DIAGNOSTIC TECHNIQUES
DISTRIBUTION
EXPERIMENT PLANNING
FLUID FLOW
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HODOSCOPES
INDUSTRIAL RADIOGRAPHY
INFORMATION
MASS
NEUTRON RADIOGRAPHY
OXIDES
OXYGEN COMPOUNDS
PLANNING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
SAFETY
SIMULATION
TEST FACILITIES
TESTING
TOMOGRAPHY
TRANSIENT OVERPOWER ACCIDENTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CHALCOGENIDES
COOLANT LOOPS
COOLING SYSTEMS
DATA
DIAGNOSTIC TECHNIQUES
DISTRIBUTION
EXPERIMENT PLANNING
FLUID FLOW
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HODOSCOPES
INDUSTRIAL RADIOGRAPHY
INFORMATION
MASS
NEUTRON RADIOGRAPHY
OXIDES
OXYGEN COMPOUNDS
PLANNING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
SAFETY
SIMULATION
TEST FACILITIES
TESTING
TOMOGRAPHY
TRANSIENT OVERPOWER ACCIDENTS