A proliferation resistant fusion breeder for thorium fuel cycle
Creators
- 1. Gazi Universitesi, Ankara (Turkey)
- 2. Nigde Universitesi, Aksaray (Turkey)
Description
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is analyzed to provide nuclear fuel for LWRs. Three different fertile material compositions are investigated for fissile fuel breeding: 1) ThO2 2) ThO2 denaturated with 10% natural-UO2 3) ThO2 denaturated with 10% LWR spent fuel. Two different coolants (pressurized helium and Flibe 'Li2BeF4') are selected for the nuclear heat transfer out of the fissile fuel breeding zone. Depending on the type of the coolant in the fission zone, fusion power plant operation periods between 30 and 48 months are evaluated to achieve a fissile fuel enrichment quality between 3% and 4%, under a first-wall fusion neutron energy load of 5 MW/m2 and a plant factor of 75%. Flibe coolant is superior to helium with regard to fissile fuel breeding. During a plant operation over four years, enrichment grades between 3.0% and 6% are calculated for different fertile fuel and coolant compositions. Fusion breeder with ThO2 produces weapon grade 233U. The denaturation of the 233U fuel is realized with a homogenous mixture of 97% ThO2 with 3% natural-UO2 as well as with 3% LWR spent nuclear fuel. The homogenous mixture of 97% ThO2 with 3% natural-UO2 can successfully denaturate 233U with 238U. However, at the early stages of plant operation, the generated plutonium component is of weapon grade quality. The plutonium component will be denaturated after a plant operation period of 24 and 30 months in Flibe cooled and gas cooled blankets, respectively. On the other hand, the homogenous mixture of 97% ThO2 with 3% LWR spent nuclear fuel remains non-prolific over the entire period for both, uranium and plutonium components. This is an important factor with regard to international safeguarding. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-114202-1
- Imprint Title
- Thorium fuel utilization: Options and trends. Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999
- Imprint Pagination
- 375 p.
- Journal Page Range
- p. 139-153
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1319
Conference
- Title
- Options and trends; Technical committee meeting on utilisation of thorium fuel; Options in emerging nuclear energy systems
- Acronym
- Advisory group meeting on thorium fuel cycle perspectives; Advisory group meeting on thorium fuel utilization
- Dates
- 16-18 Apr 1977; 28-30 Sep 1998; 15-17 Nov 1999
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33068574
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- BREEDER REACTORS; BREEDING BLANKETS; BURNUP; CALCULATION METHODS; CANDU TYPE REACTORS; FUEL MANAGEMENT; PROLIFERATION; REACTOR KINETICS; SAFETY; THORIUM CYCLE; THORIUM OXIDES; URANIUM DIOXIDE; WATER COOLED REACTORS;
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COLLOIDS; CONTRAST MEDIA; DISPERSIONS; FUEL CYCLE; HEAVY WATER MODERATED REACTORS; KINETICS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOCOLLOIDS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; THORIUM COMPOUNDS; THOROTRAST; URANIUM COMPOUNDS; URANIUM OXIDES;
Optional Information
- Lead record
- ervc8-mmb62
- Notes
- 38 refs, 10 figs, 2 tabs