Fission product behavior in LWRs. Quarterly progress report, October--December 1977. [Loss of coolant and spent fuel transportation accidents]
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the fuel was ejected from the rod as particulates. The feasibility and conceptual design study for an experimental facility to verify fission product transport computational models has been completed. Although the study focused entirely on a facility which would be employed to verify those aspects of the transport models that dealt with fission product source-term attenuation factors in the primary coolant circuit external to the pressure vessel, the need for a second facility, to simulate conditions within the pressure vessel, was also indicated.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5124935
- Report Number(s):
- ORNL/NUREG/TM-186
- Country of Publication:
- United States
- Language:
- English
Similar Records
Quarterly progress report on fission product behavior in LWRs for the period January--March 1978. [Fuel rods defected in a steam atmosphere]
Quarterly progress report on fission product behavior in LWRs, April--June 1977. [Loss of coolant and spent fuel transportation accidents]
Quarterly Progress Report on Fission Product Behavior in LWRs for the Period April-June 1978
Technical Report
·
Fri Mar 31 23:00:00 EST 1978
·
OSTI ID:6741573
Quarterly progress report on fission product behavior in LWRs, April--June 1977. [Loss of coolant and spent fuel transportation accidents]
Technical Report
·
Mon Aug 01 00:00:00 EDT 1977
·
OSTI ID:7088486
Quarterly Progress Report on Fission Product Behavior in LWRs for the Period April-June 1978
Technical Report
·
Thu Aug 31 20:00:00 EDT 1978
·
OSTI ID:6515189
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
COST
DESIGN
FISSION PRODUCT RELEASE
FUEL ELEMENTS
LEAKS
LOSS OF COOLANT
MELTDOWN
PWR TYPE REACTORS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH PROGRAMS
SPENT FUEL ELEMENTS
TEST FACILITIES
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
COST
DESIGN
FISSION PRODUCT RELEASE
FUEL ELEMENTS
LEAKS
LOSS OF COOLANT
MELTDOWN
PWR TYPE REACTORS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH PROGRAMS
SPENT FUEL ELEMENTS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS