Thermal-hydraulics and safety analyses of the Solid Core-Sectored Compact Reactor (SC-SCoRe) and power system
- 1. Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, NM (United States)
- 2. Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM (United States)
- 3. Mechanical Engineering Department, University of New Mexico, Albuquerque, NM (United States)
Description
Highlights: • Performed safety and thermal hydraulics analyses of nuclear reactor for lunar surface power. • Integrated power system nominally supplies 38 kWe to lunar outpost. • Sectored core design and power system integration avoid single point failures. • Power system supplies 4 kWe to outpost, following a loss of coolant or cooling in a core sector. - Abstract: The paper presents results of thermal-hydraulics and safety analyses of the Solid Core-Sectored Compact Reactor (SC-SCoRe) and the power system that could nominally provide 38 kWe continuously for ∼ 21 years to a lunar outpost. The power system employs static components and has no single point failures in reactor cooling and energy conversion. The monolithic-core reactor operates nominally at a thermal power of 1.0 MWth and comprises six sectors cooled with circulating liquid NaK-56 at inlet and exit temperatures of 850 K and 900 K. The sectors that are neutronically and thermally coupled each has a separate pair of primary and secondary loops with thermoelectric (TE) powered electromagnetic pumps, a TE power conversion assembly, and heat-pipes radiator panels. Performed are 3-D thermal-hydraulics and safety analyses of the SC-SCoRe during nominal operation and following the unlikely event of a loss of coolant (LOC) or a loss of cooling (LOCo) in one of the reactor core sectors. Calculated results include the flow velocity and temperature fields in the core sectors, inlet and exit ducts and upper and lower plenums. Results demonstrate that with a core sector experiencing a LOC or a LOCo, the power system could continue to operate safely at a reduced reactor power of 323 kWth, and generate four kWe for critical life support functions at the lunar outpost.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2014.05.020Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2014.05.020;
- PII
- S0149197014001395;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 76
- Journal Page Range
- p. 216-231
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51012815
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- COMPUTERIZED SIMULATION; DUCTS; ELECTROMAGNETIC PUMPS; FAILURES; HEAT PIPES; LOSS OF COOLANT; LOSS OF CORE COOLING; REACTOR CORES; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; SODIUM COMPOUNDS; THERMAL HYDRAULICS; THERMOELECTRIC CONVERSION
- Descriptors DEC
- ACCIDENTS; ALKALI METAL COMPOUNDS; CONVERSION; COOLING SYSTEMS; DIRECT ENERGY CONVERSION; ENERGY CONVERSION; ENERGY SYSTEMS; EQUIPMENT; FLUID MECHANICS; HYDRAULICS; MECHANICS; PUMPS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; SIMULATION
Optional Information
- Notes
- Copyright © 2014 Elsevier Ltd. All rights reserved.