Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to permit sweep gas analysis of short-lived fission products during a coolant blowdown in the x-2 loop

Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to permit sweep gas analysis of short-lived fission products during a coolant blowdown in the x-2 loop PDF Author: L. R. Bourque
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Languages : en
Pages : 0

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Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop while measuring the internal element gas pressure

Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop while measuring the internal element gas pressure PDF Author: L. R. Bourque
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ISBN:
Category :
Languages : en
Pages : 0

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Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop (coolant

Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop (coolant PDF Author: L. R. Bourque
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ISBN:
Category :
Languages : en
Pages : 0

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Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop

Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop PDF Author: R. W. Bull
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Languages : en
Pages : 0

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Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop. (repeat

Fabrication and pre-irradiation data for an instrumented stainless steel clad uo2 fuel element designed to be blown down in the x-2 loop. (repeat PDF Author: L. R. Bourque
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Languages : en
Pages : 0

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Fabrication and pre-irradiation data of an instrumented, zircaloy-clad uo2 fuel element designed to undergo a coolant blowdown in the x-2 loop

Fabrication and pre-irradiation data of an instrumented, zircaloy-clad uo2 fuel element designed to undergo a coolant blowdown in the x-2 loop PDF Author: A. R. Yamazaki
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Category :
Languages : en
Pages : 0

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Fabrication and pre-irradiation data for an instrumented stainless steel-clad uo2 fuel element designed to operate in intermittent dryout and to

Fabrication and pre-irradiation data for an instrumented stainless steel-clad uo2 fuel element designed to operate in intermittent dryout and to PDF Author: L. R. Bourque
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Fabrication and pre-irradiation data for three instrumented stainless steel sheathed uo2 fuel elements designed to be blown down in the x-2 loop

Fabrication and pre-irradiation data for three instrumented stainless steel sheathed uo2 fuel elements designed to be blown down in the x-2 loop PDF Author: A. R. Yamazaki
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Category :
Languages : en
Pages : 0

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Fabrication and pre-irradiation data for an instrumented zircaloy-clad uo2 fuel element designed to be blown down in the x-2 loop after pre-irradiation in the x-4 loop

Fabrication and pre-irradiation data for an instrumented zircaloy-clad uo2 fuel element designed to be blown down in the x-2 loop after pre-irradiation in the x-4 loop PDF Author: Jonckheere M.G.
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Category :
Languages : en
Pages : 0

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Production Test IP-508-D Irradiation of a Porous Stainless Steel Clad Fuel Element Assembly

Production Test IP-508-D Irradiation of a Porous Stainless Steel Clad Fuel Element Assembly PDF Author:
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Category :
Languages : en
Pages : 14

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A large number of irradiation tests have been conducted with UO2 fuel elements to characterize the behavior of Zircaloy cladding when cooling water is allowed to penetrate the cladding to the fuel core. The test element, is designed so that cooling water will be in contact with the surface of the UO2 fuel core during irradiation. The irradiation behavior of the UO2 will be compared to the behavior of similarly irradiated, non-defected UO2 fuel-elements. Several characteristics are of particular interest: (1) Previous investigations have shown that fission fragments formed in UO2 fuel cores tend to migrate from their point of formation. The fission fragment distribution in this element will be compared with that observed in other irradiated UO2 fuel cores. (2) This test will provide a direct measure of fission products released from UO2 during irradiation. (3) Sintered UO2 is quite resistant to erosion and is, in general, chemically stable in a water environment. This test will provide data concerning the dissolution rate of UO2 in water during irradiation. (4) Since the coolant will be in direct contact with the fuel, the average temperature of the fuel will be comparatively low. Therefore, the in-reactor sintering characteristics of the fuel should be different from those observed in ''normal'' fuel elements.