Application of the gas-cooled reactor data base to the estimation of LWR accident irradiation source term
Technical Report
·
OSTI ID:6635225
The fission product release data bases on high-temperature gas-cooled reactor (HTGR) and gas-cooled fast breeder reactor (GCFR) fuels have been examined to determine their usefulness in developing accident source terms for light water reactors (LWRs). The GCFR data base provided some data on the release rates of alkali metal radionuclides from GCFR fuels. These data generally support the data obtained on LWR fuels. The states of GCFR and LWR fuels prior to the initiation of a core heat-up accident are different, primarily because of the movement of fission products inside GCFR rods, a phenomenon not observed in LWRs. The HTGR data base was of very limited value because of the extreme differences between HTGR fuel and LWR fuel. An experimental program is proposed which could provide data on the effects of steam on fission product release and transport and fuel rod chemistry.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6635225
- Report Number(s):
- ALO-1014; GA-C-16798; ON: DE83005256
- Country of Publication:
- United States
- Language:
- English
Similar Records
Overview of environmental control aspects for the gas-cooled fast reactor
Fission product source terms for the LWR loss-of-coolant accident
Fission product source terms for the LWR loss-of-coolant accident
Technical Report
·
Fri May 01 00:00:00 EDT 1981
·
OSTI ID:6480553
Fission product source terms for the LWR loss-of-coolant accident
Technical Report
·
Tue Jul 01 00:00:00 EDT 1980
·
OSTI ID:5341503
Fission product source terms for the LWR loss-of-coolant accident
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6494228
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
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
BWR TYPE REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
GAS COOLED REACTORS
GCFR TYPE REACTORS
PWR TYPE REACTORS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
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
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
BWR TYPE REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
GAS COOLED REACTORS
GCFR TYPE REACTORS
PWR TYPE REACTORS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS