Fission-gas Release from Uranium Nitride at High Fission-rate Density PDF Download
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Author: Michael B. Weinstein
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 68
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Book Description
A sweep gas facility has been used to measure the release rates of radioactive fission gases from small UN specimens irradiated to 8-percent burnup at high fission-rate densities. The measured release rates have been correlated with an equation whose terms correspond to direct recoil release, fission-enhanced diffusion, and atomic diffusion (a function of temperature). Release rates were found to increase linearly with burnups between 1.5 and 8 percent. Pore migration was observed after operation at 1550 K to over 6 percent burnup.
Author: Michael B. Weinstein
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 68
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Book Description
A sweep gas facility has been used to measure the release rates of radioactive fission gases from small UN specimens irradiated to 8-percent burnup at high fission-rate densities. The measured release rates have been correlated with an equation whose terms correspond to direct recoil release, fission-enhanced diffusion, and atomic diffusion (a function of temperature). Release rates were found to increase linearly with burnups between 1.5 and 8 percent. Pore migration was observed after operation at 1550 K to over 6 percent burnup.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 32
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Author: Michael B. Weinstein
Publisher:
ISBN:
Category :
Languages : en
Pages : 22
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Author: James B. Melehan
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 62
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Author:
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Category :
Languages : en
Pages : 29
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Author: Ralph O. Meyer
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 78
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Author: Benjamin Lustman
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 72
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Author: Daniel Lee DeForest
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 0
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Book Description
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.
Author: Daniel Lee DeForest
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 466
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