Future fuel cycle development for CANDU reactors
- 1. Atomic Energy of Canada Limited Research Company, Ottawa, Ontario
Description
The CANDU reactor has proven to be safe and economical and has demonstrated outstanding performance with natural uranium fuel. The use of on-paper fueling, coupled with excellent neutron economy, leads to a very flexible reactor system which can utilize a wide variety of fuels. The spectrum of fuel cycles ranges from natural uranium, through slightly enriched uranium, to plutonium and ultimately thorium fuels which offer many of the advantages of the fast breeder reactor system. CANDU can also burn the recycled uranium and/or the plutonium from fuel discharged from light water reactors. This synergistic relationship could obviate the need to re-enrich the reprocessed uranium and allow a simpler reprocessing scheme. Fuel management strategies that will permit future fuel cycles to be used in existing CANDU reactors have been identified. Evolutionary design changes will lead to an even greater flexibility, which will guarantee the continued success of the CANDU system
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 56
- Journal Issue
- 1
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 520-526
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- 6. Pacific Basin nuclear conference.
- Dates
- 7-11 Sep 1987.
- Place
- Beijing (China).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20064302
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL CYCLE; FUEL MANAGEMENT; NATURAL URANIUM; PERFORMANCE; PLUTONIUM; REACTOR OPERATION; REPROCESSING; SLIGHTLY ENRICHED URANIUM; THORIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENRICHED URANIUM; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MANAGEMENT; MATERIALS; METALS; NUCLEAR MATERIALS MANAGEMENT; OPERATION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SEPARATION PROCESSES; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM
Optional Information
- Secondary number(s)
- CONF-870905--.