Preparation of Alloy for First Core Loading of EBR-II
Preparation of Alloy for First Core Loading of EBR-II

Author: Donald C. Hampson

Publisher:

Published: 1961

Total Pages: 38

ISBN-13:

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The alloy used for the fabrication of the fuel pins for the first core loading of the second Experimental Breeder Reactor (EBR-II) was prepared in the prototype equipment developed for the melt-refining processing of the irradiated EBR-II fuel. One hundred and twenty-five 10-kg ingots were made, of which 40 were un-enriched uranium-fissium alloy and 85 were enriched uranium-fissium alloy. In addition, nineteen 10-kg batches of un-enriched uranium-fissium scrap and forty- seven 10-kg batches of enriched uranium-fissium alloy scrap were melted for consolidation into ingots. The average yield for the alloy preparation runs was 96.5% and for the scrap remelt runs was 93%. The chemical and isotopic compositions of the ingots produced were all within specifications (95 plus or minus 1.0 wt% uranium, of which 48.1 plus or minus 1.2 wt% is U-235).

Nuclear Criticality Control in the EBR-II Fuel Cycle Facility
Nuclear Criticality Control in the EBR-II Fuel Cycle Facility

Author: J. C. Hesson

Publisher:

Published: 1964

Total Pages: 40

ISBN-13:

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An investigation has been made of criticality problems which might be encountered in EBR-II Fuel Cycle Facility. The purpose of the investigation was to determine quantity and configuration limits of the investigation was to determine quantity and configuration limits for EBR-II fuel of the first core composition during storage, handling and processing of this fuel material in the EBR-II Fuel Cycle Facility. Brief consideration in processing future EBR-II cores which are expected to contain plutonium as a fissionable matrial.

Fabrication of EBR-II, Core I Fuel Pins
Fabrication of EBR-II, Core I Fuel Pins

Author: H. F. Jelinek

Publisher:

Published: 1962

Total Pages: 36

ISBN-13:

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A total of 11,117 enriched uranium-5 wt.% fissium alloy fuel pins was manufactured for EBR-II, Core I. These were made from a synthetic fission product alloy of nonradioactive elements, natural uranium, and enriched uranium. The material was supplied as precast billets. The manufacturing methods were developed for the EBR-III Fuel Cycle Facility. Experimental refabrication equipment was used to production test both the methods and the equipment.