secondary coolant

См. также в других словарях:

• secondary coolant circuit — antrasis reaktoriaus kontūras statusas T sritis Energetika apibrėžtis Sistema, kurios paskirtis šalinti pirmojo kontūro šilumą. Antrąjį kontūrą paprastai sudaro vamzdynai, tarpiniai šilumokaičiai (garo generatoriai), garo turbinos, garo… …   Aiškinamasis šiluminės ir branduolinės technikos terminų žodynas

• Coolant — A coolant is a fluid which flows through a device to prevent its overheating, transferring the heat produced by the device to other devices that use or dissipate it. An ideal coolant has high thermal capacity, low viscosity, is low cost, non… …   Wikipedia

• Pressurized water reactor — (PWRs) (also VVER if of Russian design) are generation II nuclear power reactors that use ordinary water under high pressure (superheated water) as coolant and neutron moderator. The primary coolant loop is kept under high pressure to prevent the …   Wikipedia

• Steam generator (nuclear power) — This is an article about nuclear power plant equipment. For other uses, see steam generator. Steam generators are heat exchangers used to convert water into steam from heat produced in a nuclear reactor core. They are used in pressurized water… …   Wikipedia

• Molten salt reactor — scheme. A molten salt reactor (MSR) is a type of nuclear fission reactor in which the primary coolant, or even the fuel itself is a molten salt mixture. MSRs run at higher temperatures than water cooled reactors for higher thermodynamic… …   Wikipedia

• International Reactor Innovative and Secure — (IRIS) is a Generation IV reactor reactor design made by an international team of companies, laboratories, and universities and coordinated by Westinghouse. IRIS is hoped to open up new markets for nuclear power and make a bridge from Generation… …   Wikipedia

• Molten-Salt Reactor Experiment — MSRE plant diagram The Molten Salt Reactor Experiment (MSRE) was an experimental molten salt reactor at the Oak Ridge National Laboratory (ORNL) researching this technology through the 1960s; constructed by 1964, it went critical in 1965 and was… …   Wikipedia

• Integral Fast Reactor — The Integral Fast Reactor or Advanced Liquid Metal Reactor is a design for a nuclear fast reactor with a specialized nuclear fuel cycle. A prototype of the reactor was built in the United States, but the project was canceled by the U.S.… …   Wikipedia

• BN-600 reactor — The BN 600 reactor is a sodium cooled fast breeder reactor built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. Designed for 600 MW (electric), it produces 560 MW (electric) dispatching energy to the Middle Urals… …   Wikipedia

• Advanced Test Reactor — The Advanced Test Reactor (ATR) is a research reactor at the Idaho National Laboratory. This reactor is primarily designed and used to test materials to be used in other, larger scale and prototype reactors. It can operate at a maximum power of… …   Wikipedia

• ГОСТ Р 52776-2007: Машины электрические вращающиеся. Номинальные данные и характеристики — Терминология ГОСТ Р 52776 2007: Машины электрические вращающиеся. Номинальные данные и характеристики оригинал документа: 3.7 величина полной нагрузки (full load value): Числовое значение параметра при работе машины с полной нагрузкой. Примечание …   Словарь-справочник терминов нормативно-технической документации