Published October 14, 1998 | Version v1
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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/

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Additional details

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)

Optional Information

Contract/Grant/Project number
W-31109-ENG-38
Funding organization
US Department of Energy (United States)