Author: Publisher: ISBN: Category : Languages : en Pages : 16
Book Description
A low-enrichment uranium (LEU) irradiation test (SIMONE project) was performed in the 45 MW Petten High-flux Reactor (HFR) as part of the Reduced Enrichment for Research and Test Reactor (RERTR) program. An LEU U3Si{sub 1.6}-Al dispersion fuel element with a fuel loading of 5.5 g cm−3 was irradiated and performed well to a total burnup of 66% and a peak burnup of 85%. The swelling behavior of the fuel was similar to that observed in previous U3Si(subscript x) irradiation experiments. The resulting fuel plate thickness increases and associated changes in coolant channel cross-sections were well within acceptable limits.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The first low-enriched U[sub 3]Si[sub 2]-Al dispersion plate-type fuel element produced at the Nuclear Fuel Element Center, BATAN, Indonesia, was irradiated to a peak [sup 235]U burnup of 62%. Postirradiation examinations performed to data shows the irradiation behavior of this element to be similar to that of U[sub 3]Si[sub 2]-Al plate-type fuel produced and tested at other institutions. The main effect of irradiation on the fuel plates is a thickness increase of 30--40 [mu]m (2.5-3.0%). This thickness increase is almost entirely due to the formation of a corrosion layer (Boehmite). The contribution of fuel swelling to the thickness increase is rather small (less than 10 [mu]m) commensurate with the burnup of the fuel and the relatively moderate as-fabricated fuel volume fraction of 27% in the fuel meat.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
APPR-type dispersion fuel element specimens containing temperature to respective burnups of approximately 50, 20, and 20% of uranium with no evidence of gross dimensional changes or loss of structural integrity. Blistering and/or core cracking has occurred when sections of 17.9 wt.% UO/sub 2/ specimens irradiated to burnups over 40% of uranium were subjected to post-irradiation annealing at 600 deg F for 24 hours. Post-irradiation core hardness measurements indicate that significant differences in irradiation damage exist between the various specimen types. These data indicate that the effects of the fabrication variables investigated in this program are as follows: The severity of irradiation damage in dispersion type fuel elements is inversely proportional to the UO/sub 2/ particle size of the fabricated plate. The particle size of the UO/ sub 2/ powder used in preparation of the initial core compact and the method of preparation of the UO/sub 2/ powders largely determine the final UO/sub 2/ particle size of roll-bonded, dispersion fuel plates. The particle size of the stainless steel powder used in the initial core mixture and the degree of cold reduction during final sizing of the fuel plate are apparently of relatively minor importance, at least for the systems investigated in this program. The severity of irradiation damage is directly proportional to the fuel concentration. Where an increased fuel loading is accompanied by an increase in the loading of the B/sub 4/C burnable poison to facilitate reactor control, the possibility of serious irradiation effects is increased to an even greater degree. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages : 9
Book Description
The first low-enriched U3Si2-Al dispersion plate-type fuel element produced at the Nuclear Fuel Element Center, BATAN, Indonesia, was irradiated to a peak 235U burnup of 62%. Postirradiation examinations performed to data shows the irradiation behavior of this element to be similar to that of U3Si2-Al plate-type fuel produced and tested at other institutions. The main effect of irradiation on the fuel plates is a thickness increase of 30--40 [mu]m (2.5-3.0%). This thickness increase is almost entirely due to the formation of a corrosion layer (Boehmite). The contribution of fuel swelling to the thickness increase is rather small (less than 10 [mu]m) commensurate with the burnup of the fuel and the relatively moderate as-fabricated fuel volume fraction of 27% in the fuel meat.
Author: Publisher: ISBN: Category : Languages : en Pages : 11
Book Description
Two irradiation test vehicles, designated RERTR-1 and RERTR-2, were inserted into the Advanced Test Reactor in Idaho in August 1997. These tests were designed to obtain irradiation performance information on a variety of potential new, high-density uranium alloy dispersion fuels, including U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru and U-10Mo-0.05Sn; the intermetallic compounds U2Mo and U3Si2 were also included in the fuel test matrix. These fuels are included in the experiments as ''microplates'' (76 mm x 22 mm x 1.3 mm outer dimensions) with a nominal fuel volume loading of 25% and irradiated at relatively low temperature ((approximately) 100 C). RERTR-1 and RERTR-2 were discharged from the reactor in November 1997 and July 1998, respectively, at calculated peak fuel burnups of 45 and 71 at.%-U235. Both experiments are currently under examination at the Alpha Gamma Hot Cell Facility at Argonne National Laboratory in Chicago. This paper presents the postirradiation examination results available to date from these experiments.
Author: ![Postirradiation Examination of a Low Enriched U[sub 3]i[sub 2]-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia PDF](https://books.google.com/books/content/images/frontcover/3ErjjwEACAAJ?fife=w80-h100)
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