enow.com Web Search

Search results

  1. Results from the WOW.Com Content Network
  2. Nuclear reactor safety system - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor_safety_system

    The fuel cladding is the first layer of protection around the nuclear fuel and is designed to protect the fuel from corrosion that would spread fuel material throughout the reactor coolant circuit. In most reactors it takes the form of a sealed metallic or ceramic layer.

  3. Core damage frequency - Wikipedia

    en.wikipedia.org/wiki/Core_damage_frequency

    This risk analysis allows decision making of any changes within a nuclear power plant in accordance with legislation, safety margins, and performance strategies. A 2003 study commissioned by the European Commission remarked that "core damage frequencies of 5 × 10 −5 [per reactor-year] are a common result" or in other words, one core damage ...

  4. Category:Nuclear reactor safety - Wikipedia

    en.wikipedia.org/.../Category:Nuclear_reactor_safety

    Download as PDF; Printable version; In other projects Wikidata item; ... Pages in category "Nuclear reactor safety" The following 13 pages are in this category, out ...

  5. Loss-of-coolant accident - Wikipedia

    en.wikipedia.org/wiki/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 deal with a LOCA. Nuclear reactors generate heat internally; to remove this heat and convert it into ...

  6. Safety code (nuclear reactor) - Wikipedia

    en.wikipedia.org/wiki/Safety_code_(nuclear_reactor)

    Download as PDF; Printable version; In other projects ... In the context of nuclear reactors, a safety code is a computer program used to analyze the safety of a ...

  7. Reactor protection system - Wikipedia

    en.wikipedia.org/wiki/Reactor_protection_system

    A reactor protection system (RPS) is a set of nuclear safety and security components in a nuclear power plant designed to safely shut down the reactor and prevent the release of radioactive materials. The system can "trip" automatically (initiating a scram), or it can be tripped by the operators. Trips occur when the parameters meet or exceed ...

  8. Passive nuclear safety - Wikipedia

    en.wikipedia.org/wiki/Passive_nuclear_safety

    Passive nuclear safety is a design approach for safety features, implemented in a nuclear reactor, that does not require any active intervention on the part of the operator or electrical/electronic feedback in order to bring the reactor to a safe shutdown state, in the event of a particular type of emergency (usually overheating resulting from a loss of coolant or loss of coolant flow).

  9. Category:Nuclear reactors - Wikipedia

    en.wikipedia.org/wiki/Category:Nuclear_reactors

    Download as PDF; Printable version; ... Nuclear reactor safety (1 C, 13 P) U. Unfinished nuclear reactors (27 P) Pages in category "Nuclear reactors"