Evaluation of safety implications of control systems in LWR nuclear power plants
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Evaluation of safety implications of control systems in LWR nuclear power plants technical findings related to unresolved safety issue A-47 by A. J. Szukiewicz

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Published by Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

Subjects:

  • Nuclear reactors -- United States -- Control.,
  • Light water reactors -- United States -- Safety measures.,
  • Nuclear power plants -- United States -- Safety measures.

Book details:

Edition Notes

StatementA.J. Szukiewicz.
ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.
The Physical Object
Pagination1 v. (various pagings) ;
ID Numbers
Open LibraryOL17674222M

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@article{osti_, title = {Regulatory analysis for resolution of USI (Unresolved Safety Issue) A Safety implications of control systems in LWR (light-water reactor) nuclear power plants: Final report}, author = {Szukiewicz, A.J.}, abstractNote = {This report presents a summary of the regulatory analysis conducted by the US Nuclear Regulatory Commission staff to evaluate the value. An in-depth evaluation was performed on non-safety-related control systems (see Section 1) that are typically used during normal plant operation on four nuclear steam supply system plants: a General Electric Company boiling-water reactor, a Westinghouse 3-loop pressurized-water reactor (PWR), a Babcock Wilcox Co. (B W) once-through steam generator PWR, and a Combustion Engineering PWR . Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants John Thomas With many thanks to Francisco Lemos for the nuclear expertise provided! Safety analysis is the study, examination and description of a nuclear installation expected behavior throughout its life, under normal and transient conditions, and also under postulated events, in order to determine: a) safety margins provided in normal operation and in transient regimes; b) the adequacy of items to prevent the consequences of accidents that may : P. F. Frutuoso e Melo, I. M. S. Oliveira, P. L. Saldanha.

If you would like to learn more about the IAEA’s work, sign up for our weekly updates containing our most important news, multimedia and more. INTERNATIONAL ATOMIC ENERGY AGENCY, Design of Instrumentation and Control Systems for Nuclear Power Plants, IAEA Safety Standards Series No. SSG, IAEA, Vienna (). Description. This publication establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. LWR Safety Analysis and Licensing and Implications for Advanced Reactors 63 ‘Risk insig hts’ is used to refer to the re sults and de cisions tha t are made after probabilistic. These control rods can be partially inserted into the reactor core to reduce the reactions. The control rods are very important because the reaction could run out of control if fission events are extremely frequent. In modern nuclear power plants, the insertion of all the control rods into the reactor core occurs in a few seconds, thus halting.

Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards (Safety Report Ser. Series, 12) [Iaea] on *FREE* shipping on qualifying offers. Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards (Safety Report Ser. Series, 12)Author: Iaea. This article covers the technical aspects of active nuclear safety systems in the United States. For a general approach to nuclear safety, see nuclear safety.. The three primary objectives of nuclear reactor safety systems as defined by the U.S. Nuclear Regulatory Commission are to shut down the reactor, maintain it in a shutdown condition and prevent the release of radioactive material. The nuclear industry and the U.S. Nuclear Regulatory Commission (USNRC) have been working for several years on the development of an adequate process to guide the replacement of aging analog monitoring and control instrumentation in nuclear power plants with modern digital instrumentation without introducing off-setting safety problems. licentiate of engineering entitled “Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems”, which was published in by the Chalmers University of Technology. Contact person SSM: Yvonne Johansson Reference: SSM