moderator temperature 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

• Neutron moderator — Currently operating nuclear power reactors by moderator Moderator Reactors Design Country none (fast) 1 BN 600 Russia (1) graphite 29 AGR, Magnox, RBMK United Kingdom (18), Russia (11) heavy water 29 CANDU …   Wikipedia

• Neutron temperature — A chart displaying the speed probability density functions of the speeds of a few noble gases at a temperature of 298.15 K (25 C). An explanation of the y axis label appears on the image page (click to see). Similar speed distributions are… …   Wikipedia

• Subcritical reactor — A subcritical reactor is a nuclear fission reactor that produces fission without achieving criticality. Instead of a sustaining chain reaction, a subcritical reactor uses additional neutrons from an outside source. A reactor coupled to a particle …   Wikipedia

• температурный коэффициент замедлителя — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN moderator temperature coefficientMTC …   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

• Organically moderated and cooled reactor — The organic moderated and cooled reactor (OCR) was an early power reactor concept studied in the formative years of nuclear power by the United States Atomic Energy Commission and others around the world. The concept reactor was very similar to… …   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

• SL-1 — The SL 1, or Stationary Low Power Reactor Number One, was a United States Army experimental nuclear power reactor which underwent a steam explosion and meltdown in January 1961, killing its three operators. The direct cause was the improper… …   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