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Supercritical water reactor
The supercritical water reactor (SCWR) is a Generation IV reactor concept that uses supercritical water (referring to the critical point of water, not the critical mass of the nuclear fuel) as the working fluid. SCWRs resemble light water reactors (LWRs) but operate at higher pressure and temperature, with a direct once-through cycle like a boiling water reactor (BWR), and the water always in a single, fluid state like the pressurized water reactor (PWR). The BWR, PWR and supercritical steam generator are all proven technologies. The SCWR is a promising advanced nuclear system because of its high thermal efficiency (~45% vs. ~33% for current LWRs) and simpler design, and is being investigated by 32 organizations in 13 countries.
==History==
SCWRs were experimented with in both Soviet Union and in the United States as early as the 1950s and 1960s. The idea however went on a 30-year hiatus, only to recently come into focus again. The first two units (now closed) at the Beloyarsk Nuclear Power Station were of SCWR type.
A 2013 document saw the completion of a prototypical fueled loop test in 2015.〔https://www.gen-4.org/gif/upload/docs/application/pdf/2013-09/gif_rd_outlook_for_generation_iv_nuclear_energy_systems.pdf〕 A Fuel Qualification Test was completed in 2014.〔http://cordis.europa.eu/result/rcn/165557_en.html〕
抄文引用元・出典: フリー百科事典『 ウィキペディア（Wikipedia）』
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