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RISS 인기검색어
- 검색키워드
- 저자 : Mujid Kazimi (검색결과 5 건)
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Superheated Water-Cooled Small Modular Underwater Reactor Concept
Koroush Shirvan,Mujid Kazimi 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.6
A novel fully passive small modular superheated water reactor (SWR) for underwater deployment is designed to produce 160 MWe with steam at 500ºC to increase the thermodynamic efficiency compared with standard light water reactors. The SWR design is based on a conceptual 400-MWe integral SWR using the internally and externally cooled annular fuel (IXAF). The coolant boils in the external channels throughout the core to approximately the same quality as a conventional boiling water reactor and then the steam, instead of exiting the reactor pressure vessel, turns around and flows downward in the central channel of some IXAF fuel rods within each assembly and then flows upward through the rest of the IXAF pins in the assembly and exits the reactor pressure vessel as superheated steam. In this study, new cladding material to withstand high temperature steam in addition to the fuel mechanical and safety behavior is investigated. The steam temperature was found to depend on the thermal and mechanical characteristics of the fuel. The SWR showed a very different transient behavior compared with a boiling water reactor. The inter-play between the inner and outer channels of the IXAF was mainly beneficial except in the case of sudden reactivity insertion transients where additional control consideration is required.
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이유호,Thomas J. Mckrell,Mujid S. Kazimi 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.6
SiC has been under investigation as a potential cladding for LWR fuel, due to its high melting point and drasticallyreduced chemical reactivity with liquid water, and steam at high temperatures. As SiC is a brittle material its behavior duringthe reflood phase of a Loss of Coolant Accident (LOCA) is another important aspect of SiC that must be examined as part ofthe feasibility assessment for its application to LWR fuel rods. In this study, an experimental assessment of thermal shockperformance of a monolithic alpha phase SiC tube was conducted by quenching the material from high temperature (up to1200ºC) into room temperature water. Post-quenching assessment was carried out by a Scanning Electron Microscopy (SEM)image analysis to characterize fractures in the material. This paper assesses the effects of pre-existing pores on SiC claddingbrittle fracture and crack development/propagation during the reflood phase. Proper extension of these guidelines to anSiC/SiC ceramic matrix composite (CMC) cladding design is discussed.
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Lee, Youho,Mckrell, Thomas J.,Kazimi, Mujid S. Korean Nuclear Society 2013 Nuclear Engineering and Technology Vol.45 No.6
SiC has been under investigation as a potential cladding for LWR fuel, due to its high melting point and drastically reduced chemical reactivity with liquid water, and steam at high temperatures. As SiC is a brittle material its behavior during the reflood phase of a Loss of Coolant Accident (LOCA) is another important aspect of SiC that must be examined as part of the feasibility assessment for its application to LWR fuel rods. In this study, an experimental assessment of thermal shock performance of a monolithic alpha phase SiC tube was conducted by quenching the material from high temperature (up to $1200^{\circ}C$) into room temperature water. Post-quenching assessment was carried out by a Scanning Electron Microscopy (SEM) image analysis to characterize fractures in the material. This paper assesses the effects of pre-existing pores on SiC cladding brittle fracture and crack development/propagation during the reflood phase. Proper extension of these guidelines to an SiC/SiC ceramic matrix composite (CMC) cladding design is discussed.
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Technology Selection for Offshore Underwater Small Modular Reactors
Koroush Shirvan,Ronald Ballinger,Jacopo Buongiorno,Charles Forsberg,Mujid Kazimi,Neil Todreas 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.6
This work examines the most viable nuclear technology options for future underwaterdesigns that would meet high safety standards as well as good economic potential, forconstruction in the 2030-2040 timeframe. The top five concepts selected from a survey of 13 nuclear technologies were compared to a small modular pressurized water reactor(PWR) designed with a conventional layout. In order of smallest to largest primary systemsize where the reactor and all safety systems are contained, the top five designs were: (1) aleadebismuth fast reactor based on the Russian SVBR-100; (2) a novel organic cooledreactor; (3) an innovative superheated water reactor; (4) a boiling water reactor based onToshiba's LSBWR; and (5) an integral PWR featuring compact steam generators. A similarstudy on potential attractive power cycles was also performed. A condensing and recompressionsupercritical CO2 cycle and a compact steam Rankine cycle were designed. It wasfound that the hull size required by the reactor, safety systems and power cycle can besignificantly reduced (50-80%) with the top five designs compared to the conventionalPWR. Based on the qualitative economic consideration, the organic cooled reactor andboiling water reactor designs are expected to be the most cost effective options.
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