High-temperature Transient Fission-gas Release from UO2 Fuel

High-temperature Transient Fission-gas Release from UO2 Fuel
Title High-temperature Transient Fission-gas Release from UO2 Fuel PDF eBook
Author P. J. Fehrenbach
Publisher
Pages 17
Release 1988
Genre
ISBN

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Fission gas release from uranium dioxide in high temperature transients

Fission gas release from uranium dioxide in high temperature transients
Title Fission gas release from uranium dioxide in high temperature transients PDF eBook
Author G. J. Small
Publisher
Pages
Release 1988
Genre Fission gases
ISBN

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Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications

Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications
Title Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications PDF eBook
Author Daniel Lee DeForest
Publisher
Pages 0
Release 1991
Genre Fission gases
ISBN

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In order to investigate whether fission gas swelling and release would be significant factors in a space based nuclear reactor operating under the Strategic Defense Initiative (SDI) program, the finite element program REDSTONE (Routine for Evaluating Dynamic Swelling in Transient Operational Nuclear Environments) was developed to model the 1-D, spherical geometry diffusion equations describing transient fission gas behavior in a single uranium nitride fuel grain. The equations characterized individual bubbles, rather than bubble groupings. This limited calculations to those scenarios where low temperatures, low burnups, or both were present. Instabilities in the bubble radii calculations forced the implementation of additional constraints limiting the bubble sizes to minimum and maximum (equilibrium) radii. The validity of REDSTONE calculations were checked against analytical solutions for internal consistency and against experimental studies for agreement with swelling and release results. These checks indicated that REDSTONE was satisfactorily accounting for the intragranular fission gas portion of swelling, but that other non-gaseous sources accounted for up to 1.5% additional swelling. A calculation was performed to determine the swelling and gas release associated with a hypothetical SDI scenario. The SDI scenario involved 10 years of low power operation at 10 kW followed by a 30 second rise to 1 MW which was maintained for approximately 15 minutes. The results indicated that the fuel pellet diametral increase would remain less than 1% and release would be negligible, far below that needed for design failure. This same scenario was run at higher temperatures to see if uncertainties in the operating parameters could cause significantly different results. It was apparent that further investigations into the swelling behavior near 1800°K were needed, as results indicated a significant shift to larger bubbles at this temperature. In an effort to understand the effect of property uncertainties on the solution, several of the properties were varied and the results compared. The largest effects were observed from changes in the irradiation enhanced diffusion coefficient and the resolution parameter. The resolution parameter uncertainty would have the largest potential effect on results, likely resulting in a reduction in the swelling and a corresponding increase in release.

Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications

Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications
Title Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications PDF eBook
Author Daniel Lee DeForest
Publisher
Pages 466
Release 1991
Genre Nuclear fuels
ISBN

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Fission Gas Release from Fuel at High Burnup

Fission Gas Release from Fuel at High Burnup
Title Fission Gas Release from Fuel at High Burnup PDF eBook
Author Ralph O. Meyer
Publisher
Pages 78
Release 1978
Genre Fission gases
ISBN

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Release of Fission Gases from U02

Release of Fission Gases from U02
Title Release of Fission Gases from U02 PDF eBook
Author Benjamin Lustman
Publisher
Pages 72
Release 1957
Genre Fission gases
ISBN

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Fission-product Release from UO2

Fission-product Release from UO2
Title Fission-product Release from UO2 PDF eBook
Author W. B. Cottrell
Publisher
Pages 148
Release 1960
Genre Nuclear merchant ships
ISBN

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