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Preliminary Assessment of Heavy-Water Thorium Reactors in the Brazilian Nuclear Programme

Conference:

Abstract

Since December 1965, the Instituto de Pesquisas Radioativas has been studying for the Brazilian Nuclear Energy Commission the feasibility of a thorium reactor programme in Brazil; since June 1966, the programme has been developed in close co-operation with the French Atomic Energy Commission. A reference conceptual design of a heavy-water-cooled and -moderated thorium converter reactor has been developed. The main features of that concept are the use of a prestressed-concrete pressure vessel, integrated arrangement of the primary circuit and the possibility of on-load fuel management. Economic competitiveness could be the result of high compactness, low capital costs and low fuel consumption. The technology involved is not very sophisticated; intensive engineering development work must be done in areas like fuel charge machine, concrete vessel insulation, and proper design of heat exchangers, but it is the feeling of the Group that these problems could be solved without seriously compromising the economic feasibility of the concept. Preliminary studies were made on the alternative use of enriched uranium or plutonium as a feed for the programme; in the latter case, plutonium could be produced in natural uranium reactors of the same type. The general conditions favouring each of these approaches to the thorium cycle  More>>
Authors:
Salvo Brito, S. de; Lepecki, W. P.S. [1] 
  1. Instituto de Pesquisas Radioativas, Belo Horizonte (Brazil)
Publication Date:
Apr 15, 1968
Product Type:
Conference
Report Number:
IAEA-SM-99/26
Resource Relation:
Conference: Symposium on Heavy-Water Power Reactors, Vienna (Austria), 11-15 Sep 1967; Other Information: 20 refs., 7 figs., 3 tabs.; Related Information: In: Heavy-Water Power Reactors. Proceedings of the Symposium on Heavy-Water Power Reactors| 1001 p.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CAPITALIZED COST; ENRICHED URANIUM; FISSILE MATERIALS; FUEL CONSUMPTION; FUEL MANAGEMENT; HEAT EXCHANGERS; HEAVY WATER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; PLUTONIUM; PRESSURE VESSELS; PRESTRESSED CONCRETE; THORIUM CYCLE; THORIUM REACTORS
OSTI ID:
22117079
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M1031073700
Submitting Site:
INIS
Size:
page(s) 451-466
Announcement Date:
Aug 01, 2013

Conference:

Citation Formats

Salvo Brito, S. de, and Lepecki, W. P.S. Preliminary Assessment of Heavy-Water Thorium Reactors in the Brazilian Nuclear Programme. IAEA: N. p., 1968. Web.
Salvo Brito, S. de, & Lepecki, W. P.S. Preliminary Assessment of Heavy-Water Thorium Reactors in the Brazilian Nuclear Programme. IAEA.
Salvo Brito, S. de, and Lepecki, W. P.S. 1968. "Preliminary Assessment of Heavy-Water Thorium Reactors in the Brazilian Nuclear Programme." IAEA.
@misc{etde_22117079,
title = {Preliminary Assessment of Heavy-Water Thorium Reactors in the Brazilian Nuclear Programme}
author = {Salvo Brito, S. de, and Lepecki, W. P.S.}
abstractNote = {Since December 1965, the Instituto de Pesquisas Radioativas has been studying for the Brazilian Nuclear Energy Commission the feasibility of a thorium reactor programme in Brazil; since June 1966, the programme has been developed in close co-operation with the French Atomic Energy Commission. A reference conceptual design of a heavy-water-cooled and -moderated thorium converter reactor has been developed. The main features of that concept are the use of a prestressed-concrete pressure vessel, integrated arrangement of the primary circuit and the possibility of on-load fuel management. Economic competitiveness could be the result of high compactness, low capital costs and low fuel consumption. The technology involved is not very sophisticated; intensive engineering development work must be done in areas like fuel charge machine, concrete vessel insulation, and proper design of heat exchangers, but it is the feeling of the Group that these problems could be solved without seriously compromising the economic feasibility of the concept. Preliminary studies were made on the alternative use of enriched uranium or plutonium as a feed for the programme; in the latter case, plutonium could be produced in natural uranium reactors of the same type. The general conditions favouring each of these approaches to the thorium cycle have been determined, in particular those related to the costs of the fissile materials in the world market and to the country's policy related to nuclear fuel imports. The results of the preliminary studies are very encouraging and could justify the beginning of a research and development programme leading to the construction of a prototype in the 1970's. (author)}
place = {IAEA}
year = {1968}
month = {Apr}
}