Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Fission product signatures measured during the PBF power cooling mismatch and reactivity initiated accident experiments. [PWR; BWR]

Conference ·
OSTI ID:6350266
; ;
Fission product release from light water reactor-type fuel rods to the coolant loop during design basis accident tests is the subject of this paper. 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 included 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 also discussed. Time-dependent release fractions for short-lived fission products are presented and compared with release fractions suggested by the Reactor Safety Study, NRC Regulatory Guides, and measurements from the Three Mile Island accident.
Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6350266
Report Number(s):
EGG-M-02881; CONF-810667-2; ON: DE81028275
Country of Publication:
United States
Language:
English

Similar Records

Fission-product-release signatures for LWR fuel rods failed during PCM and RIA transients
Conference · Wed Dec 31 23:00:00 EST 1980 · OSTI ID:5698517
Reactivity initiated accident test series Test RIA 1-4 fuel behavior report. [PWR; BWR]
Technical Report · Sat Sep 01 00:00:00 EDT 1984 · OSTI ID:6338876
Reactivity initiated accident test series Test RIA 1-4
Technical Report · Thu May 01 00:00:00 EDT 1980 · OSTI ID:5569467

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
ACTIVITY LEVELS
BWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
ISOTOPE RATIO
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS