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Title: Thermal-hydraulics and safety analysis of sectored compact reactor for lunar surface power

Abstract

The liquid NaK-cooled, fast-neutron spectrum, Sectored Compact Reactor (SCoRe-N 5) concept has been developed at the Univ. of New Mexico for lunar surface power applications. It is loaded with highly enriched UN fuel pins in a triangular lattice, and nominally operates at exit and inlet coolant temperatures of 850 K and 900 K. This long-life reactor generates up to 1 MWth continuously for {>=} 20 years. To avoid a single point failure in reactor cooling, the core is divided into 6 sectors that are neutronically and thermally coupled, but hydraulically independent. This paper performs a 3-D the thermal-hydraulic analysis of SCoRe--N 5 at nominal operation temperatures and a power level of 1 MWth. In addition, the paper investigates the potential of continuing reactor operation at a lower power in the unlikely event that one sector in the core experiences a loss of coolant (LOC). Redesigning the core with a contiguous steel matrix enhances the cooling of the sector experiencing a LOC. Results show that with a core sector experiencing a LOC, SCORE-N 5 could continue operating safely at a reduced power of 166.6 kWth. (authors)

Authors:
 [1];  [2];  [1];  [2];  [2]
  1. Inst. for Space and Nuclear Power Studies, Univ. of New Mexico, Albuquerque, NM (United States)
  2. (United States)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22106038
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 13 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FAST NEUTRONS; FUEL PINS; LIQUID METAL COOLED REACTORS; LOSS OF COOLANT; MOON; POTASSIUM ALLOYS; REACTOR CORES; REACTOR OPERATION; SAFETY ANALYSIS; SODIUM ALLOYS; SPACE POWER REACTORS; THERMAL HYDRAULICS; URANIUM NITRIDES; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

Schriener, T. M., Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM, El-Genk, M. S., Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM, and Mechanical Engineering Dept., Univ. of New Mexico, Albuquerque, NM. Thermal-hydraulics and safety analysis of sectored compact reactor for lunar surface power. United States: N. p., 2012. Web.
Schriener, T. M., Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM, El-Genk, M. S., Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM, & Mechanical Engineering Dept., Univ. of New Mexico, Albuquerque, NM. Thermal-hydraulics and safety analysis of sectored compact reactor for lunar surface power. United States.
Schriener, T. M., Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM, El-Genk, M. S., Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM, and Mechanical Engineering Dept., Univ. of New Mexico, Albuquerque, NM. Sun . "Thermal-hydraulics and safety analysis of sectored compact reactor for lunar surface power". United States.
@article{osti_22106038,
title = {Thermal-hydraulics and safety analysis of sectored compact reactor for lunar surface power},
author = {Schriener, T. M. and Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM and El-Genk, M. S. and Chemical and Nuclear Engineering Dept., Univ. of New Mexico, Albuquerque, NM and Mechanical Engineering Dept., Univ. of New Mexico, Albuquerque, NM},
abstractNote = {The liquid NaK-cooled, fast-neutron spectrum, Sectored Compact Reactor (SCoRe-N 5) concept has been developed at the Univ. of New Mexico for lunar surface power applications. It is loaded with highly enriched UN fuel pins in a triangular lattice, and nominally operates at exit and inlet coolant temperatures of 850 K and 900 K. This long-life reactor generates up to 1 MWth continuously for {>=} 20 years. To avoid a single point failure in reactor cooling, the core is divided into 6 sectors that are neutronically and thermally coupled, but hydraulically independent. This paper performs a 3-D the thermal-hydraulic analysis of SCoRe--N 5 at nominal operation temperatures and a power level of 1 MWth. In addition, the paper investigates the potential of continuing reactor operation at a lower power in the unlikely event that one sector in the core experiences a loss of coolant (LOC). Redesigning the core with a contiguous steel matrix enhances the cooling of the sector experiencing a LOC. Results show that with a core sector experiencing a LOC, SCORE-N 5 could continue operating safely at a reduced power of 166.6 kWth. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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