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The BR2 materials testing reactor. Past, ongoing and under-study upgradings

Abstract

The BR2 reactor (Mol, Belgium) is a high-flux materials testing reactor. The fuel is 93% {sup 235}U enriched uranium. The nominal power ranges from 60 to 100 MW. The main features of the design are the following: 1) maximum neutron flux, thermal: 1.2 x 10{sup 15} n/cm{sup 2} s; fast (E > 0.1 MeV) : 8.4 x 10{sup 14} n /cm{sup 2} s; 2) great flexibility of utilization: the core configuration and operation mode can be adapted to the experimental loading; 3) neutron spectrum tailoring; 4) availability of five 200 mm diameter channels besides the standard channels (84 mm diameter); 5) access to the top and bottom covers of the reactor authorizing the irradiation of loops. The reactor is used to study the behaviour of fuel elements and structural materials intended for future nuclear power stations of several types (fission and fusion). Irradiations are carried out in connection with performance tests up to very high burn-up or neutron fluence as well as for safety experiments, power cycling experiments, and generally speaking, tests under off-normal conditions. Irradiations for nuclear transmutation (production of high specific activity radio-isotopes and transplutonium elements), neutron-radiography, use of beam tubes for physics studies, and gamma irradiations are  More>>
Authors:
Baugnet, J M; Roedt, Ch de; Gubel, P; Koonen, E [1] 
  1. Centre d'Etude de I'Energie Nucleaire, Studiecentrum voor Kernenergie, C.E.N./S.C.K., Mol (Belgium)
Publication Date:
May 01, 1990
Product Type:
Conference
Report Number:
CONF-9002100; INIS-XA-C-023
Resource Relation:
Conference: IGORR 1: 1. meeting of the International Group On Research Reactors, Knoxville, TN (United States), 28 Feb - 2 Mar 1990; Other Information: 4 refs, 14 figs, 1 tab; PBD: May 1990; Related Information: In: IGORR 1: Proceedings of the 1. meeting of the International Group On Research Reactors, by West, C.D. (comp.), 282 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BR-2 REACTOR; BUILDING MATERIALS; BURNUP EXTENSION; FAST NEUTRONS; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; ISOTOPE PRODUCTION; MATERIALS TESTING; NEUTRON FLUENCE; NEUTRON FLUX; NEUTRON SPECTRA; REACTOR EXPERIMENTAL FACILITIES; REACTOR OPERATION; SAFETY; THERMAL NEUTRONS
OSTI ID:
20571795
Research Organizations:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA04C1608023805
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
34 pages
Announcement Date:
Mar 20, 2005

Citation Formats

Baugnet, J M, Roedt, Ch de, Gubel, P, and Koonen, E. The BR2 materials testing reactor. Past, ongoing and under-study upgradings. IAEA: N. p., 1990. Web.
Baugnet, J M, Roedt, Ch de, Gubel, P, & Koonen, E. The BR2 materials testing reactor. Past, ongoing and under-study upgradings. IAEA.
Baugnet, J M, Roedt, Ch de, Gubel, P, and Koonen, E. 1990. "The BR2 materials testing reactor. Past, ongoing and under-study upgradings." IAEA.
@misc{etde_20571795,
title = {The BR2 materials testing reactor. Past, ongoing and under-study upgradings}
author = {Baugnet, J M, Roedt, Ch de, Gubel, P, and Koonen, E}
abstractNote = {The BR2 reactor (Mol, Belgium) is a high-flux materials testing reactor. The fuel is 93% {sup 235}U enriched uranium. The nominal power ranges from 60 to 100 MW. The main features of the design are the following: 1) maximum neutron flux, thermal: 1.2 x 10{sup 15} n/cm{sup 2} s; fast (E > 0.1 MeV) : 8.4 x 10{sup 14} n /cm{sup 2} s; 2) great flexibility of utilization: the core configuration and operation mode can be adapted to the experimental loading; 3) neutron spectrum tailoring; 4) availability of five 200 mm diameter channels besides the standard channels (84 mm diameter); 5) access to the top and bottom covers of the reactor authorizing the irradiation of loops. The reactor is used to study the behaviour of fuel elements and structural materials intended for future nuclear power stations of several types (fission and fusion). Irradiations are carried out in connection with performance tests up to very high burn-up or neutron fluence as well as for safety experiments, power cycling experiments, and generally speaking, tests under off-normal conditions. Irradiations for nuclear transmutation (production of high specific activity radio-isotopes and transplutonium elements), neutron-radiography, use of beam tubes for physics studies, and gamma irradiations are also carried out. The BR2 is used in support of Belgian programs, at the request of utilities, industry and universities and in the framework of international agreements. The paper reviews the past and ongoing upgrading and enhancement of reactor capabilities as well as those under study or consideration, namely with regard to: reactor equipment, fuel elements, irradiation facilities, reactor operation conditions and long-term strategy. (author)}
place = {IAEA}
year = {1990}
month = {May}
}