Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Ehud Greenspan

关键词: AFTER-HEAT REMOVAL;    BUILDING MATERIALS;    COOLING SYSTEMS;    CROSS SECTIONS;    DEPLETED URANIUM;    ECONOMIC ANALYSIS;    FUEL RODS;    HEAT PIPES;    HEAT SOURCES;    HEAT TRANSFER;    HEXAGONAL LATTICES;    HYDROGEN PRODUCTION;    NATURAL CONVECTION;    NUCLEAR ENERGY;    REACTIVITY COEFFICIENTS;    REACTOR SAFETY;    REACTOR VESSELS;    REACTORS;    SAFETY ANALYSIS;    SPENT FUELS;    WORKING FLUIDS;   

DOI  :  10.2172/940911
RP-ID  :  DOE/ID/14706
PID  :  OSTI ID: 940911
Others  :  TRN: US0807271

美国|英语

来源: SciTech Connect

【 摘 要 】

This project was devoted to a preliminary assessment of the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor to have a solid core from which heat is removed by liquid-metal heat pipes (HP).