Fission-product-release signatures for LWR fuel rods failed during PCM and RIA transients
Conference
·
OSTI ID:5698517
This paper discusses fission product release from light-water-reactor-type fuel rods to the coolant loop during design basis accident tests. One of the tests was a power-cooling-mismatch test in which a single fuel rod was operated in film boiling beyond failure. Other tests discussed include reactivity initiated accident (RIA) tests, in which the fuel rods failed as a result of power bursts that produced radial-average peak fuel enthalpies ranging from 250 to 350 cal/g. One of the RIA tests used two previously irradiated fuel rods. On-line gamma spectroscopic measurements of short-lived fission products, and important aspects of fission product behavior observed during the tests, are discussed. Time-dependent release fractions for short-lived fission products are compared with release fractions suggested by: the Reactor Safety Study; NRC Regulatory Guides; and measurements from the Three Mile Island accident. Iodine behavior observed during the tests is discussed, and fuel powdering is identified as a source of particulate fission product activity, the latter of which is neglected for most accident analyses.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5698517
- Report Number(s):
- CONF-810803-17; ON: DE82005260
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fission product signatures measured during the PBF power cooling mismatch and reactivity initiated accident experiments. [PWR; BWR]
Reactivity initiated accident test series Test RIA 1-4
Kinetics Calculations for RIA Experiments in the Power Burst Facility
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6350266
Reactivity initiated accident test series Test RIA 1-4
Technical Report
·
Thu May 01 00:00:00 EDT 1980
·
OSTI ID:5569467
Kinetics Calculations for RIA Experiments in the Power Burst Facility
Technical Report
·
Tue Oct 23 00:00:00 EDT 1979
·
OSTI ID:1462032
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS