Published October 14, 1998
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A neutronics feasibility study for the LEU conversion of Poland's Maria research reactor
Description
The MARIA reactor is a high-flux multipurpose research reactor which is water-cooled and moderated with both beryllium and water. Standard HEU (80% 235U)fuel assemblies consist of six concentric fuel tubes of a U-Al alloy clad in aluminum. Although the inventory of HEU (80%) fuel is nearly exhausted, a supply of highly-loaded 36%-enriched fuel assemblies is available at the reactor site. Neutronic equilibrium studies have been made to determine the relative performance of fuels with enrichments of 80%, 36% and 19.7%. These studies indicate that LEU (19.7%) densities of about 2.5 gU/cm3 and 3.8 gU/cm3 are required to match the performance of the MARIA reactor with 80%-enriched and with 36%-enriched fuels, respectively
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00011047; PURL: https://www.osti.gov/servlets/purl/11047-9w02Tf/webviewable/Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- ANL/TD/CP--97463
Conference
- Title
- 21. International Meeting on Reduced Enrichment for Research and Test Reactors
- Dates
- 18-23 Oct 1998
- Place
- Sao Paulo (Brazil)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 32067898
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM ALLOYS; FEASIBILITY STUDIES; FUEL ASSEMBLIES; HIGHLY ENRICHED URANIUM; MARIA REACTOR; PERFORMANCE; SLIGHTLY ENRICHED URANIUM; URANIUM ALLOYS
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDES; ALLOYS; BERYLLIUM MODERATED REACTORS; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; METAL MODERATED REACTORS; METALS; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- W-31109-ENG-38
- Funding organization
- US Department of Energy (United States)