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 |
Swelling in Uranium
Title | Swelling in Uranium PDF eBook |
Author | T. K. Bierlein |
Publisher | |
Pages | 40 |
Release | 1961 |
Genre | Annealing of metals |
ISBN |
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 |
SWELLING OF URANIUM. Report
Title | SWELLING OF URANIUM. Report PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1963 |
Genre | |
ISBN |
SWELLING OF URANIUM (Second Year of Study).
Title | SWELLING OF URANIUM (Second Year of Study). PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1965 |
Genre | |
ISBN |
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 |
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 |
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.