Data summary report for fission product release test HI-1. [PWR; BWR]
Technical Report
·
OSTI ID:6547277
This first in a series of high-temperature fission product release tests was conducted for 30 min at 1400/sup 0/C, with the release taking place into flowing steam. The fuel specimen was a 20-cm-long section of H.B. Robinson fuel rod, irradiated to 28,000 MWd per metric ton (t). After the test, the Zircaloy cladding of the specimen was almost completely oxidized and was quite fragile. The fission product collection system included a thermal gradient tube (700-150/sup 0/C), filters, heated charcoal, and cooled charcoal. Gamma ray analysis of apparatus components and collectors showed that about 2.83% of the /sup 85/Kr and 1.75% of the /sup 137/Cs were released from the fuel. Activation analysis of leach solutions from these components indicated that 2.04% of the /sup 129/I was released. Other analyses revealed small but significant releases of the radionuclides /sup 125/Sb and /sup 106/Ru, and of the elements Br, Rb, Sr, Zr, Ag, Sn, Te, Ba, and La.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6547277
- Report Number(s):
- NUREG/CR-2928; ORNL/TM-8500; ON: DE83005886
- Country of Publication:
- United States
- Language:
- English
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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
ALLOYS
BWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STEAM
STRESSES
TEMPERATURE GRADIENTS
THERMAL STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
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
ALLOYS
BWR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STEAM
STRESSES
TEMPERATURE GRADIENTS
THERMAL STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS