Title: PHASE III FUEL SAMPLE IRRADIATION. IRRADIATION REQUEST ORNL-21

The integrity and suitability of 35 vol.% U/sub 3/ O/sub 8/ dispersion in Al as a fuel for foreign reactors were determined. The fuel was exposed in the beryllium reflector of the MTR. Sample fabrication and conditions of exposurne are described, and the results are tabulated. (J.R.D.)

The following data summarize the results of calculations presented in this report to determine the irradiation testing for Phase I of Irradiation Request ORNLMTR-35. This phase of the program entails exposure of a 48 wt.% U-3 wt.% Si-49 wt.% Al alloys inthe beryllium reflector of the MTR. (auth)

>lium reflector of the MTR to burn-up values of 20, 40, 60, and 80% of the U/sup 235/ atoms is described. The fuel

A series of im-pile fuel sample irradiation experiments was initiated to obtaim radiation damage information on fuel material combinations applicable to Foreign Reactor Program Fuel Elements where U/sup 235/ enrichment is limited to 20%. The series of expcriments will be divided into several phases, each being based on the materials combination employed. This report describes Phase I of the program which consists of determining the integrity and suitability of a 48 wt.% U--3 wt.% Si-49 wt.% Al alloy as a fuel for Foreign Reactor Fuel Elements. (auth)