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Title: A neutronics feasibility study for the LEU conversion of Poland's Maria research reactor.

Conference ·
OSTI ID:11047

The MARIA reactor is a high-flux multipurpose research reactor which is water-cooled and moderated with both beryllium and water. Standard HEU (80% {sup 235}U)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/cm{sup 3} and 3.8 gU/cm{sup 3} are required to match the performance of the MARIA reactor with 80%-enriched and with 36%-enriched fuels, respectively.

Research Organization:
Argonne National Lab., IL (US)
Sponsoring Organization:
US Department of Energy (US)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
11047
Report Number(s):
ANL/TD/CP-97463; TRN: US0104237
Resource Relation:
Conference: 21st International Meeting on Reduced Enrichment for Research and Test Reactors, Sao Paulo (BR), 10/18/1998--10/23/1998; Other Information: PBD: 14 Oct 1998
Country of Publication:
United States
Language:
English