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sodium void reactivity coefficient

См. также в других словарях:

  • Void coefficient — In nuclear engineering, the void coefficient (more properly called void coefficient of reactivity ) is a number that can be used to estimate how much the reactivity of a nuclear reactor changes as voids (steam bubbles) form in the reactor… …   Wikipedia

  • натриевый пустотный коэффициент реактивности — (ядерного реактора с натриевым теплоносителем) [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN sodium void reactivity coefficientSVRC …   Справочник технического переводчика

  • Nuclear meltdown — Three of the reactors at Fukushima I overheated, causing core meltdowns. This was compounded by hydrogen gas explosions and the venting of contaminated steam which released large amounts of radioactive material into the air.[1] …   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

  • Passive nuclear safety — describes a safety feature of a nuclear reactor that does not require operator action or electronic feedback in order to shut down safely in the event of a particular type of emergency (usually overheating resulting from a loss of coolant or loss …   Wikipedia

  • Nuclear reactor physics — See also: Critical mass Nuclear reactor physics is the branch of science that deals with the study and application of chain reaction to induce controlled rate of fission for energy in reactors. Most nuclear reactors use a chain reaction to induce …   Wikipedia

  • Fast neutron reactor — [ Shevchenko BN350 nuclear fast reactor and desalination plant situated on the shore of the Caspian Sea. The plant generates 135 MWe and provides steam for an associated desalination plant. View of the interior of the reactor hall.] A fast… …   Wikipedia

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