Improving fuel utilization in SmAHTR with spectral shift control design: Proof of concept
Creators
- 1. Georgia Institute of Technology, George W. Woodruff School, Nuclear and Radiological Engineering, Atlanta, GA 30332-0405 (United States)
- 2. Amec Foster Wheeler, Dorchester (United Kingdom)
- 3. Department of Engineering, University of Cambridge, Cambridge CB2 1PZ (United Kingdom)
Description
Highlights: • Improving the fuel utilization in a graphite moderated reactor by adopting the 'spectral shift' concept. • The feasibility of this concept was tested in the Small Advanced High-Temperature Reactor. • At BOL, the reactor is under-moderated, with excess neutrons being primarily breeding 239Pu. • Graphite is continuously inserted thermalizing the neutron spectrum and increasing reactivity. • The extra 239Pu bred during the cycle is then burned, allowing the cycle to be extended. - Abstract: This paper presents a spectral shift design based approach to improve the fuel utilization factor or alternatively to increase the cycle length in a graphite moderated reactor. The feasibility of this concept was tested in the Small Advanced High-Temperature Reactor (SmAHTR). This is a small sized Fluoride-salt-cooled high-temperature reactor (FHR) that uses tri-isotropic (TRISO)-coated particle fuels and graphite moderator materials. A major benefit of the TRISO particles is the ability to mitigate fission product release in the case of an accident. However, the fabrication costs associated with TRISO particles are expected to be significantly higher than the traditional UO2 fuel. The preliminary studies presented in the paper are focused on extending the achievable irradiation period without increasing the value of the enrichment. In order to increase the discharge burnup, the design includes graphite structures that are initially removed from the core. This imposes a harder spectrum, which enhances the breeding of 239Pu. Then, the graphite structures are gradually and continuously inserted into the core to sustain criticality. This procedure shifts the hard spectrum into a more thermal one and enables a more efficient utilization of 239Pu. The preliminary results indicate that this design achieves considerably longer irradiation periods and hence lower fuel cycle costs than the reference design.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.12.037Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.12.037;
- PII
- S0306-4549(16)30444-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 104
- Journal Page Range
- p. 53-63
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48086644
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; CRITICALITY; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL CYCLE; GRAPHITE; GRAPHITE MODERATED REACTORS; IRRADIATION; MOLTEN SALT COOLED REACTORS; NEUTRONS; NUCLEAR FUELS; PLUTONIUM 239; REACTIVITY; REACTOR ACCIDENTS; REACTOR DESIGN; SPECTRAL SHIFT CONTROL; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYONS; CARBON; CHALCOGENIDES; CONFIGURATION CONTROL; CONTROL; DESIGN; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; FERMIONS; FUELS; HADRONS; HEAVY NUCLEI; ISOTOPES; MATERIALS; MINERALS; MOLTEN SALT REACTORS; NONMETALS; NUCLEI; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM ISOTOPES; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM COMPOUNDS; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.