Study and design of a molten salt reactor for power supply in space: first glimpse of the core design
- 1. Universite Grenoble-Alpes, Ecole doctorale I-MEP2, 110 rue de la Chimie, 38400 Saint-Martin-d'Heres (France)
- 2. Universite Paris-Saclay, CEA - Centre de Saclay, Service d'Etudes et de Mathematiques Appliquees - SERMA, 91191 Gif-sur-Yvette (France)
- 3. Centre National de la Recherche Scientifique, CNRS Grenoble, 25, rue des Martyrs, B.P. 166, 38042 Grenoble Cedex 9 (France)
Description
As new space missions are planned, longer and more ambitious, the need for a controllable powerful energy becomes a priority. Though electric propulsion still suffers from its very low thrust, advanced designs like NASA's X3 or Ad Astra Rocket Company's VASIMR are filling the gap at the price of a great power supply need. Given this context, we began the study of a 1 MWe reactor for space application. Because of its inherent safety, as well as its high controllability allowing quick power changes, we choose the molten salt reactor technology. The presented work relates to the building of the core design based on the technology of molten salt reactors, already taking into account technological and safety constraints. Initial calculations motivated the choice of a thermal graphite-moderated reactor using a U235 highly enriched fluoride salt. A study of different configurations and the sensibility of the criticality to some variations of the design, as well as some identified constraints on the system, then oriented the work toward the proposed design. Once a design chosen, the reactivity reserve and the Doppler effect compensation have been studied. This last point is essential to ensure an autonomous start-up of the core, an easier design and the possibility to shut-down and restart the reactor several times as a solid salt means no density negative feedback. Otherwise, the core could not reach on its own its operating temperature without an additional and independent core heater system to melt the salt. Eventually lifespan issues through Monte-Carlo burn-up calculations on the proposed design have been investigated. (authors)
Availability note (English)
Available (CD Rom) from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-787-3
- Imprint Title
- Proceedings of the international conference on physics of reactors - PHYSOR 2022
- Imprint Pagination
- 3701 p.
- Journal Page Range
- p. 3434-3443
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR 2022
- Dates
- 15-20 May 2022
- Place
- Pittsburg (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54042201
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICALITY; GRAPHITE MODERATED REACTORS; LITHIUM COOLED REACTORS; MOLTEN SALT FUELED REACTORS; REACTOR CORES; SPACE POWER REACTORS; SPECIFICATIONS
- Descriptors DEC
- FLUID FUELED REACTORS; LIQUID METAL COOLED REACTORS; MOBILE REACTORS; MOLTEN SALT REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION
Optional Information
- Notes
- 14 refs.