CORROSION TESTING OF URANIUM SILICIDE FUEL SPECIMENS.
Technical Report
·
OSTI ID:4822650
U{sub 3}Si is the most promising high density natural uranium fuel for water-cooled power reactors. Power reactors fuelled with this material are expected to produce cheaper electricity than those fuelled with uranium dioxide. Corrosion tests in 300 degC water preceded extensive in-reactor performance tests of fuel elements and bundles. Proper heat-treatment of U-3.9 wt% Si gives a U{sub 3}Si specimen which corrodes at less than 2 mg/cm{sup 2} h in 300 degC water. This is an order of magnitude lower than the maximum corrosion rate tolerable in a water-cooled reactor. U{sub 3}Si in a defected unbonded Zircaloy-2 sheath showed only a slow uniform sheath expansion in 300 degC water. All tests were done under isothermal conditions in an out-reactor loop.
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River (Ontario) Canada. Chalk River Nuclear Labs.
- NSA Number:
- NSA-23-012388
- OSTI ID:
- 4822650
- Report Number(s):
- AECL--2718
- Country of Publication:
- Canada
- Language:
- English
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Related Subjects
CORROSION
FUEL CANS
FUELS
N30210* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Corrosion & Erosion & Surface Phenomena
POWER
REACTOR FUELS/corrosion testing of zircaloy-clad uranium silicide
in 300$sup 0$C water
REACTORS
REACTORS
WATER-COOLED/fuel for
corrosion testing of zircaloy-clad uranium silicide
TEMPERATURE
TESTING
URANIUM SILICIDES
URANIUM SILICIDES/corrosion testing of zircaloy-clad reactor fuel of
in 300$sup 0$C water
WATER
ZIRCALOY
FUEL CANS
FUELS
N30210* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Corrosion & Erosion & Surface Phenomena
POWER
REACTOR FUELS/corrosion testing of zircaloy-clad uranium silicide
in 300$sup 0$C water
REACTORS
REACTORS
WATER-COOLED/fuel for
corrosion testing of zircaloy-clad uranium silicide
TEMPERATURE
TESTING
URANIUM SILICIDES
URANIUM SILICIDES/corrosion testing of zircaloy-clad reactor fuel of
in 300$sup 0$C water
WATER
ZIRCALOY