Parametric neutronics analyses of lattice geometry and coolant candidates for a soluble-boron-free civil marine SMR core using micro-heterogeneous duplex fuel
- 1. French Alternative Energies and Atomic Energy Commission, 13115 Saint-Paul-lez-Durance (France)
- 2. Department of Engineering, University of Cambridge, Cambridge CB2 1PZ (United Kingdom)
- 3. Rhode Island Atomic Energy Commission, 16 Reactor Rd, Narragansett, RI 02882 (United States)
Description
Highlights: • No study has been performed for mixed D2O-H2O coolant with soluble-boron-free SMR. • Neutron spectrum variation over burnup is observed for mixed D2O-H2O coolant. • Wetter-than-normal or dryer-than-normal lattice are better for higher burnup. • D2O-H2O and H2O are effective for the drier and wetter lattices, respectively. • Duplex fuel offers higher discharge burnup potential for all moderation regimes. - Abstract: Civilian marine reactors face a unique set of design challenges in addition to the usual irradiation and thermal-hydraulic limits affecting all reactors. These include requirements for a small core size, long core lifetime, a 20% cap on fissile loading, and limitations on the use of soluble boron. One way to achieve higher burnup/longer core life is to alter the neutron spectrum by changing the hydrogen-to-heavy-metal ratio, thus increasing the conversion of fertile isotopes in the fuel. In this reactor physics study, we optimize the two-dimensional lattice geometry of a 333 MWth soluble-boron-free marine PWR for 18% 235U enriched micro-heterogeneous ThO2-UO2 duplex fuel and 15% 235U enriched homogeneously mixed all-UO2 fuel. We consider two types of coolant: H2O and mixed 80% D2O + 20% H2O. We aim to observe in which spectrum discharge burnup is maximized in order to improve uranium utilization, while satisfying the constraint on moderator temperature coefficient. It is observed that higher discharge burnup for the candidate fuels is achievable by using either a wetter lattice or a much drier lattice than normal, while epithermal lattices are distinctly inferior performers. The thorium-rich duplex fuel exhibits higher discharge burnup potential than the all-UO2 fuel for all moderation regimes for both coolants. The candidate fuels exhibit higher initial reactivity and discharge burnup with the mixed D2O-H2O coolant than with the H2O coolant in the under-moderated regime, whereas these values are lower for the D2O-H2O coolant in the over-moderated regime.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.01.037Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.01.037;
- PII
- S0306454919300362;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 129
- Journal Page Range
- p. 1-12
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51008036
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP EXTENSION; CONVERSION RATIO; FERTILE MATERIALS; FISSIONABLE MATERIALS; HEAVY METALS; HEAVY WATER; HYDROGEN; MODERATELY ENRICHED URANIUM; NEUTRON SPECTRA; PWR TYPE REACTORS; REACTOR PHYSICS; SHIP PROPULSION REACTORS; SMALL MODULAR REACTORS; TEMPERATURE COEFFICIENT; THERMAL HYDRAULICS; THORIUM; THORIUM OXIDES; TWO-DIMENSIONAL CALCULATIONS; URANIUM 235; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; BURNUP; CHALCOGENIDES; DEUTERIUM COMPOUNDS; DIMENSIONLESS NUMBERS; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; FLUID MECHANICS; HEAVY NUCLEI; HYDRAULICS; HYDROGEN COMPOUNDS; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; MECHANICS; METALS; MINUTES LIVING RADIOISOTOPES; NONMETALS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PHYSICS; POWER REACTORS; PROPULSION REACTORS; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTORS; SPECTRA; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; THORIUM COMPOUNDS; URANIUM; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
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