Summary report on fuel development and miniplate fabrication for the RERTR Program, 1978 to 1990
- 1. Argonne National Lab., IL (United States). Energy Technology Div.
Description
This report summarizes the efforts of the Fabrication Technology Section at Argonne National Laboratory in the program of Reduced Enrichment Research and Test Reactors (RERTR). The main objective of this program was to reduce the amount of high enriched (∼93% 235U) uranium (HEU) used in nonpower reactors. Conversion from low-density (0.8--1.6 g U/cm3) HEU fuel elements to highly loaded (up to 7 g U/cm3) low-enrichment (<20% 235U) uranium (LEU) fuel elements allows the same reactor power levels, core designs and sizes to be retained while greatly reducing the possibility of illicit diversion of HEU nuclear fuel. This document is intended as an overview of the period 1978--1990, during which the Section supported this project by fabricating mainly powder metallurgy uranium-silicide dispersion fuel plates. Most of the subjects covered in detail are fabrication-related studies of uranium silicide fuels and fuel plate properties. Some data are included for out-of-pile experiments such as corrosion and compatibility tests. Also briefly covered are most other aspects of the RERTR program such as irradiation tests, full-core demonstrations, and technology transfer. References included are for further information on most aspects of the entire program. A significant portion of the report is devoted to data that were never published in their entirety. The appendices contain a list of previous RERTR reports, ANL fabrication procedures, calculations for phases present in two-phase fuels, chemical analysis of fuels, miniplate characteristics, and a summary of bonding runs made by hot isostatic pressing
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE96004025; NTIS; US Govt. Printing Office Dep.Files
27032064.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 244 p.
- Report number
- ANL--RERTR/TM-15
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27032064
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DATA; DISPERSION NUCLEAR FUELS; FABRICATION; FUEL PLATES; HIGHLY ENRICHED URANIUM; MATERIAL SUBSTITUTION; MODERATELY ENRICHED URANIUM; NUCLEAR FUELS; NUCLEAR MATERIALS DIVERSION; PERFORMANCE; PERFORMANCE TESTING; RESEARCH AND TEST REACTORS; URANIUM SILICIDES; URANIUM 235
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; EVEN-ODD NUCLEI; FUEL ELEMENTS; FUELS; HEAVY NUCLEI; INFORMATION; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SILICIDES; SILICON COMPOUNDS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; TESTING; URANIUM; URANIUM COMPOUNDS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- USDOE, Washington, DC (United States).