Fission product release from simulated LWR fuel. [Loss of coolant or spent fuel transportation accident conditions]
A series of tests has been conducted with simulated LWR fuel as part of a program for determining the quantities and characteristics of radiologically significant fission products that can be released under postulated spent-fuel transportation accident (SFTA) conditions and successfully terminated loss-of-coolant accident (LOCA) conditions. These tests were performed in either flowing-steam or dry-air atmospheres with Zircaloy-4-clad fuel-rod segments that contained unirradiated UO/sub 2/ pellets coated with radioactively traced CsOH, CsI, and TeO/sub 2/. A summary of the test conditions and amounts released are given. Cesium release associated with the implanted CsOH appeared to be limited by the formation of low-volatility uranate compounds. Iodine release was observed primarily as CsI, but also as I/sub 2/; in addition, at test temperatures of 900/sup 0/C and above, significant migration of the CsI to the cooler ends of the fuel-rod segments was noted. Tellurium release was markedly restricted by rapid reaction with the Zircaloy cladding. The tests in air yielded enhanced releases of cesium and iodine, and considerable swelling of the oxidized UO/sub 2/. As anticipated, measured release fractions were greater when the test rods were ruptured at temperature by internal pressure than when the cladding failures were machined in the rods prior to testing.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6558307
- Report Number(s):
- NUREG/CR-0274; ORNL/NUREG/TM-154; TRN: 79-002039
- Country of Publication:
- United States
- Language:
- English
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BWR TYPE REACTORS
FUEL ELEMENTS
FISSION PRODUCT RELEASE
PWR TYPE REACTORS
SPENT FUEL ELEMENTS
HIGH TEMPERATURE
LOSS OF COOLANT
SIMULATION
TRANSPORT
VERY HIGH TEMPERATURE
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