moderator void coefficient

moderator void coefficient
пустотный коэффициент реактивности замедлителя

[lang name="English"]total diffusion coefficient — суммарный коэффициент диффузии

[lang name="English"]sample coefficient — коэффициент отбора; коэффициент выборки

[lang name="English"]coefficient of rolling friction — коэффициент трения качения

[lang name="English"]spectral coefficient — коэффициент спектрального разложения

[lang name="English"]lift coefficient curve — кривая коэффициента подъемной силы


English-Russian dictionary on nuclear energy. 2015.

Игры ⚽ Поможем написать курсовую

Смотреть что такое "moderator void coefficient" 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

  • Prompt critical — In nuclear engineering, an assembly is prompt critical if for each nuclear fission event, one or more of the immediate or prompt neutrons released causes an additional fission event. This causes a rapidly exponential increase in the number of… …   Wikipedia

  • 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

  • Chernobyl disaster — This article is about the 1986 nuclear plant accident in Ukraine. For other uses, see Chernobyl (disambiguation). Chernobyl disaster …   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

  • RBMK — is an acronym for the Russian reaktor bolshoy moshchnosti kanalniy ( ru. Реактор Большой Мощности Канальный) which means High Power Channel Type Reactor , and describes a class of graphite moderated nuclear power reactor which was built in the… …   Wikipedia

  • Loss of coolant accident — A loss of coolant accident (LOCA) is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor core damage. Each nuclear plant s Emergency Core Cooling System (ECCS) exists specifically to… …   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

  • 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

  • Dampfblasenkoeffizient — Der Dampfblasenkoeffizient (auch Kühlmittelverlustkoeffizient oder Voidkoeffizient genannt) ist ein Maß für die Veränderung der Reaktivität eines Kernreaktors bei Bildung von Dampfblasen im Kühlmittel oder im Moderator. Eine Reaktivitätsänderung …   Deutsch Wikipedia


Поделиться ссылкой на выделенное

Прямая ссылка:
Нажмите правой клавишей мыши и выберите «Копировать ссылку»