Swelling in Alpha Uranium Due to Irradiation

Swelling in Alpha Uranium Due to Irradiation
Title Swelling in Alpha Uranium Due to Irradiation PDF eBook
Author S.F. Pugh
Publisher
Pages 24
Release 1960
Genre
ISBN

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Irradiation Damage and Swelling in Alpha Uranium

Irradiation Damage and Swelling in Alpha Uranium
Title Irradiation Damage and Swelling in Alpha Uranium PDF eBook
Author Brian Hudson
Publisher
Pages
Release 1974
Genre
ISBN

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Irradiation Swelling of Uranium and Uranium Alloys

Irradiation Swelling of Uranium and Uranium Alloys
Title Irradiation Swelling of Uranium and Uranium Alloys PDF eBook
Author Gordon G. Bentle
Publisher
Pages 76
Release 1961
Genre Nuclear fuel elements
ISBN

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A Metallographic Study of the Swelling of Uranium and Uranium Alloys

A Metallographic Study of the Swelling of Uranium and Uranium Alloys
Title A Metallographic Study of the Swelling of Uranium and Uranium Alloys PDF eBook
Author A. Boltax
Publisher
Pages 80
Release 1960
Genre Uranium
ISBN

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Swelling in Uranium

Swelling in Uranium
Title Swelling in Uranium PDF eBook
Author T. K. Bierlein
Publisher
Pages 40
Release 1961
Genre Annealing of metals
ISBN

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Swelling of Uranium and Uranium Alloys on Postirradiation Annealing

Swelling of Uranium and Uranium Alloys on Postirradiation Annealing
Title Swelling of Uranium and Uranium Alloys on Postirradiation Annealing PDF eBook
Author B. A. Loomis
Publisher
Pages 46
Release 1962
Genre Fuel burnup (Nuclear engineering).
ISBN

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The swelling of uranium and of a few selected uranium alloys on post-irradiation annealing was investigated by utilizing density measurements in conjunction with the observation of pores in the microstructures of annealed specimens. Specimens were irradiated to about 0.3 at.% burnup in a constrained condition at approximately 275 deg C and were subsequently pulse annealed. The amount of swelling was found to be less than 1% for U specimens that were pulse annealed up to 75 hr at temperatures below 550 deg C; the amount of swelling, however, increased considerably on annealing at temperatures between 550 and 650 deg C. Specimens pulse annealed up to 75 hr at 618 deg C decreased in density by approximately 18%. The swelling was accompanied by the formation of bubbles on grain boundaries in recrystallized regions. The observations suggest that recrystallization is a necessary prerequisite for pronounced swelling in the alpha phase.

Fission Gas Bubble Nucleated Cavitational Swelling of the Alpha-uranium Phase of Irradiated U-Pu-Zr Fuel

Fission Gas Bubble Nucleated Cavitational Swelling of the Alpha-uranium Phase of Irradiated U-Pu-Zr Fuel
Title Fission Gas Bubble Nucleated Cavitational Swelling of the Alpha-uranium Phase of Irradiated U-Pu-Zr Fuel PDF eBook
Author
Publisher
Pages 20
Release 1992
Genre
ISBN

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Cavitational swelling has been identified as a potential swelling mechanism for the alpha uranium phase of irradiated U-Pu-Zr metal fuels for the Integral Fast Reactor being developed at Argonne National Laboratory. The trends of U-Pu-Zr swelling data prior to fuel cladding contact can be interpreted in terms of unrestrained cavitational driven swelling. It is theorized that the swelling mechanisms at work in the alpha uranium phase can be modeled by single vacancy and single interstitial kinetics with intergranular gas bubbles providing the void nuclei, avoiding the use of complicated defect interaction terms required for the calculation of void nucleation. The focus of the kinetics of fission gas evolution as it relates to cavitational swelling is prior to the formation of a significant amount of interconnected porosity and is on the development of small intergranular gas bubbles which can act as void nuclei. Calculations for the evolution of intergranular fission gas bubbles show that they provide critical cavity sizes (i.e., the size above which the cavity will grow by bias-driven vacancy flux) consistent with the observed incubation dose for the onset of rapid swelling and gas release.