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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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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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 OF URANIUM. Report

SWELLING OF URANIUM. Report
Title SWELLING OF URANIUM. Report PDF eBook
Author
Publisher
Pages
Release 1963
Genre
ISBN

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SWELLING OF URANIUM (Second Year of Study).

SWELLING OF URANIUM (Second Year of Study).
Title SWELLING OF URANIUM (Second Year of Study). PDF eBook
Author
Publisher
Pages
Release 1965
Genre
ISBN

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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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Uranium Swelling in N-Reactor (PT-NR-4, Sup. A, Report No. 1).

Uranium Swelling in N-Reactor (PT-NR-4, Sup. A, Report No. 1).
Title Uranium Swelling in N-Reactor (PT-NR-4, Sup. A, Report No. 1). PDF eBook
Author
Publisher
Pages 15
Release 1965
Genre
ISBN

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Five monitor columns, containing some pre-irradiation weighed inner and outer fuel elements, were discharged under authorization of PT-NR-4, Sup A at tube average exposures in the range from 1554 to 1631 MWD/T. Uranium swelling values have been calculated from post-irradiation weight measurements and these swelling values have been compared with those swelling values obtained in the KER loop tests. There is acceptable agreement between KER and NPR results for swelling of inner uranium; there is acceptable agreement for outer fuel elements at higher exposures but ends-of-the-column elements (i.e. low-exposure values) are not in agreement. The current swelling values have been extrapolated to determine the tube-average exposure that will result in outer clad strains of one percent. At this conservative value of clad strain, one can predict entirely adequate performance of outer fuel elements to tube average exposures of 2200 MWD/T and inner fuel elements to 2700 MWD/T tube average exposure. Elements that will soon be discharged at tube average exposures ranging from 1900 to 2100 MWD/T, can be evaluated for swelling during the next outage and a much better prediction can be made on the relation of exposure vs swelling and hence exposure vs fuel element integrity. The continuing objective of this production test remains as the determination of fuel element performance vs exposure.