Published 2002 | Version v1
Conference paper Open

A preliminary study on the suitability of high density LEU fuel elements to maintain BR2 reactor operational characteristics

Creators

  • 1. BR2 Department Belgian Nuclear Research Centre, SCK-CEN, B-2400 MOL (Belgium)

Description

The present international efforts to develop high density fuel based on U-Mo (6-9%wt) triggered the present preliminary study to analyse the suitability of these high density LEU fuels to maintain the operational characteristics of the BR2 reactor. The analyses concern the perturbation mode in a fuel cell for determining the available thermal neutron flux, the power generated, Pu-239 production and reactivity variation versus the burnup of fuel elements loaded in a cell where the statistical weight is unitary. The comparison with several types of fuel elements used at the BR2 reactor gives preliminary answers asked for using LEU fuel type in the BR2 reactor. (author)

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Part of:
ENS RRFM 2002, Transactions. Oral Presentations and Posters

Additional details

Publishing Information

Publisher
European Nuclear Society
Imprint Place
Berne (Switzerland)
Imprint Title
ENS RRFM 2002, Transactions. Oral Presentations and Posters
Imprint Pagination
p. 83-87
Report number
INIS-CH--0302

Conference

Title
6th International Topical Meeting on Research Reactor Fuel Management, organized by the ENS in cooperation with the Belgian Nuclear Energy Society and the IAEA
Acronym
RRFM 2002
Dates
17-20 Mar 2002
Place
Ghent (Belgium)

INIS

Country of Publication
Switzerland
Country of Input or Organization
Switzerland
INIS RN
34030701
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BR-02 REACTOR; ENRICHED URANIUM; FUEL MANAGEMENT; NUCLEAR FUELS; NUMERICAL DATA; RESEARCH REACTORS; SAFETY
Descriptors DEC
ACTINIDES; BERYLLIUM MODERATED REACTORS; DATA; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; INFORMATION; ISOTOPE ENRICHED MATERIALS; MANAGEMENT; MATERIALS; METAL MODERATED REACTORS; METALS; NUCLEAR MATERIALS MANAGEMENT; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 fig., 2 tabs., 4 refs.