Author: M. L. Swanson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination of high-power density uc fuel elements from WR-1
The post-irradiation examination of a 21-element, uo2 fuel bundle irradiated in WR-1
Post-irradiation examination of a specially modified 14-element uc bundle, gl-280w, from the WR-1 8th charge
A proposal to irradiate high-power density uc elements in WR-1
Post-irradiation examination of sap-clad uc fuel from the wr1-951 and 952 experiments
An addendum to the proposal to irradiate high-power-density uc elements in WR-1
A proposal to irradiate high power density uo2 fuel elements in WR-1
Post-irradiation examination of WR-1-viii(oz)2 fuel channel
Proposal for a high power density, uranium-graphite fuel irradiation in WR-1
Postirradiation Examination of High-density Uranium Alloy Dispersion Fuels
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.
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.