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core damage probability

См. также в других словарях:

  • Core damage frequency — (CDF) is a term used in probabilistic risk assessment (PRA) that indicates the likelihood of an accident that would cause damage to a nuclear reactor core.[1][2][3] Core damage accidents are considered serious because damage to the core may… …   Wikipedia

  • вероятность повреждения активной зоны ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN core damage probabilityCDP …   Справочник технического переводчика

  • условия вероятность повреждения активной зоны ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN conditional core damage probabilityCCDP …   Справочник технического переводчика

  • International Nuclear Event Scale — The International Nuclear and Radiological Event Scale (INES) was introduced in 1990[1] by the International Atomic Energy Agency (IAEA) in order to enable prompt communication of safety significance information in case of nuclear accidents. The… …   Wikipedia

  • List of mathematics articles (C) — NOTOC C C closed subgroup C minimal theory C normal subgroup C number C semiring C space C symmetry C* algebra C0 semigroup CA group Cabal (set theory) Cabibbo Kobayashi Maskawa matrix Cabinet projection Cable knot Cabri Geometry Cabtaxi number… …   Wikipedia

  • NUREG-1150 — ( Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants , 1991, by the Nuclear Regulatory Commission [NRC]) is an improvement on WASH 1400 and CRAC II using the results of plant specific Probabilistic Risk Assessments (PRAs). It …   Wikipedia

  • Gerald W. Brown — is an American whistleblower, who concerned himself with deficiencies in passive fire protection systems in US and Canadian nuclear power plants.Thermo Lag scandalGerald W. Brown was the original whistleblower of the Thermo Lag 330 1 scandal [… …   Wikipedia

  • Economic Simplified Boiling Water Reactor — The reactor formally known as Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor which builds on the success of the ABWR. Both are designs by General Electric, and are based on their BWR design.The ESBWR …   Wikipedia

  • Nuclear power in the United States — For a comprehensive list of U.S. plants, see List of nuclear reactors. NRC regions and locations of nuclear reactors, 2008 Main article: Nuclear power As of 2008, nuclear power in the United States is provided by 104 commercial reactors (69 …   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

  • AP1000 — Westinghouse Electric Company s AP1000 reactor design is the first Generation III+ reactor to receive final design approval from the NRC.cite web | title =AP 1000 Public Safety and Licensing | work = | publisher =Westinghouse | date =2004 09 13 | …   Wikipedia

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