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of three candidate locations where a VHTR can be built. The popularity on the VHTR, therefore, grows. Hopefully, this will change Americans’ perception of nuclear reactors if the energy crisis and ozone layer depletion from fossil power plant CO2 emissions get more serious. The VHTR has several advantages over light water reactors. These include fuel integrity, a proliferation-resistant and relatively simple fuel cycle, online fuel maintenance, and modularity for remote areas needing electricity and for the energy-starved underdeveloped countries with little power generation infrastructure. In addition to the modularity, the VHTR offers unique simplicity (single-phase), scalability, and structural volume (10 kW/ft2 for VHTR versus 6 kW/ft2 for AP-1000). However, some technical and economical challenges must be overcome, particularly reactor safety and costs. Our concerns about the VHTR are its economics and the technical problems of materials exposed to the high- temperature environment. The VHTR (current reference design by INEEL and MIT [INEEL, 1999, Nicholas, 2001]) or prismatic fuel modular reactor (PMR) technologies will lead to industrial projects that will satisfactorily meet Generation IV goals and will be judged to be deployable about 2010 to 2015. These HTGR systems rely on strongly synergetic research work: High-temperature capability steels for both reactor plant and power conversion applications High-temperature systems technology. Since VHTRs are high-temperature gas reactors, material behavior for long periods of time will require sustainability and confirmation. Operation temperatures below 1000C can be realized with available material and knowledge, unless new materials are developed or new surface applications are developed. Higher temperatures need considerable material qualification and development of new high- temperature alloys, special treatment surfaces, or fiber-reinforced ceramics and compounds. Without development of new materials, at 950 to 1000C the lifetime of available high-temperature alloys will be limited. Components exposed to high temperature may have to be replaced every 15 to 20 years if no better materials can be qualified [Generation IV Roadmap, 2001]. Replacement will be a challenge for the design (e.g., modular arrangements), whereas improving high-temperature alloys or surface coatings remains a medium-term R&D task. Again, the VHTR offers an alternative approach to commercializing nuclear power, compared to other fission-power-producing systems such as light water reactors, and liquid metal-cooled fast breeder reactors. Gas cooling for nuclear reactors had been considered in the United States. The fundamental design of the VHTR is aimed at achieving a system without any physical process that could cause an internally or externally induced radiation hazard outside the site boundary. The thermal-hydraulic stabilization is achieved by modularizing the core with a relatively low-power density (<4.5MW/m3), such that the integrated heat loss capability from the reactor exceeds the decay heat production of the core under all conceivable accident conditions. Using helium as a coolant, which is both chemically and radiogically inert, combined with the improved net plant efficiency achieved by using supercritical carbon dioxide in the secondary side, allows using a high primary-coolant temperature (950oC), which yields high thermal efficiencies. In conclusion, plant design should be streamlined for technically sound, robust, passively safe, and low-cost production. Although gas reactors were developed in the past with limited success, the innovations of modularity and integrated state-of-art passive safety systems, coupled with improved safety design and plant efficiencies, make this design potentially very attractive from a technical and economic perspective. 2PDF Image | Development Of A Supercritical Carbon Dioxide Brayton Cycle
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