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Predicted irradiation behavior of U3O8-Al dispersion fuels for production reactor applications.

DE91005099

Publication Date	1990
Personal Author	Cronenberg, A. W.; Rest, J.; Hyder, M. L.; Morin, J. P.; Peacock, H. B.
Page Count	17
Abstract	Candidate fuels for the new heavy-water production reactor include uranium/aluminum alloy and U(sub 3)O(sub 8)--Al dispersion fuels. The U(sub 3)O(sub 8)--Al dispersion fuel would make possible higher uranium loadings and would facilitate uranium recycle. Research efforts on U(sub 3)O(sub 8)--Al fuel include in-pile irradiation studies and development of analytical tools to characterize the behavior of dispersion fuels at high-burnup. In this paper the irradiation performance of U(sub 3)O(sub 8)--Al is assessed using the mechanistic Dispersion Analysis Research Tool (DART) code. Predictions of fuel swelling and alteration of thermal conductivity are presented and compared with experimental data. Calculational results indicate good agreement with available data where the effects of as-fabricated porosity and U(sub 3)O(sub 8)--Al oxygen exchange reactions are shown to exert a controlling influence on irradiation behavior. The DART code is judged to be a useful tool for assessing U(sub 3)O(sub 8)--Al performance over a wide range of irradiation conditions. 8 refs., 8 figs., 1 tab.
Keywords	Dispersion Nuclear Fuels Production Reactors Aluminium Burnup D Codes Irradiation Mathematical Models Nuclear Fuels Performance Porosity Stresses Swelling Thermal Conductivity Uranium Oxides U3O8 Meetings EDB/220700 EDB/220300 Ceramics Physical radiation effects
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77I - Reactor Fuels & Fuel Processing
Corporate Authors	Westinghouse Savannah River Co., Aiken,SC.; Department of Energy, Washington, DC.
Supplemental Notes	American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	199108
Contract Number	AC09-89SR18035

Predicted irradiation behavior of U3O8-Al dispersion fuels for production reactor applications.

Predicted irradiation behavior of U3O8-Al dispersion fuels for production reactor applications.
DE91005099

Publication Date	1990
Personal Author	Cronenberg, A. W.; Rest, J.; Hyder, M. L.; Morin, J. P.; Peacock, H. B.
Page Count	17
Abstract	Candidate fuels for the new heavy-water production reactor include uranium/aluminum alloy and U(sub 3)O(sub 8)--Al dispersion fuels. The U(sub 3)O(sub 8)--Al dispersion fuel would make possible higher uranium loadings and would facilitate uranium recycle. Research efforts on U(sub 3)O(sub 8)--Al fuel include in-pile irradiation studies and development of analytical tools to characterize the behavior of dispersion fuels at high-burnup. In this paper the irradiation performance of U(sub 3)O(sub 8)--Al is assessed using the mechanistic Dispersion Analysis Research Tool (DART) code. Predictions of fuel swelling and alteration of thermal conductivity are presented and compared with experimental data. Calculational results indicate good agreement with available data where the effects of as-fabricated porosity and U(sub 3)O(sub 8)--Al oxygen exchange reactions are shown to exert a controlling influence on irradiation behavior. The DART code is judged to be a useful tool for assessing U(sub 3)O(sub 8)--Al performance over a wide range of irradiation conditions. 8 refs., 8 figs., 1 tab.
Keywords	Dispersion Nuclear Fuels Production Reactors Aluminium Burnup D Codes Irradiation Mathematical Models Nuclear Fuels Performance Porosity Stresses Swelling Thermal Conductivity Uranium Oxides U3O8 Meetings EDB/220700 EDB/220300 Ceramics Physical radiation effects
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77I - Reactor Fuels & Fuel Processing
Corporate Authors	Westinghouse Savannah River Co., Aiken,SC.; Department of Energy, Washington, DC.
Supplemental Notes	American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	199108
Contract Number	AC09-89SR18035