Reactor coolant and associated systems in nuclear power plants
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Reactor coolant and associated systems in nuclear power plants a safety guide. by International Atomic Energy Agency.

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Published by The Agency in Vienna .
Written in English


  • Nuclear reactors -- Safety measures,
  • Nuclear reactors -- Cooling,
  • Nuclear power plants -- Safety measures.

Book details:

Edition Notes

SeriesSafety series -- no. 50-SG-D13. IAEA safety guides, Safety series (International Atomic Energy Agency) -- no. 50-SG-D13
LC ClassificationsTK9152 I548 1986
The Physical Object
Pagination70 p. :
Number of Pages70
ID Numbers
Open LibraryOL20978037M
ISBN 10920123886X

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Reactor coolant and associated systems in nuclear power plants. Vienna: International Atomic Energy Agency, (OCoLC) Material Type: Government publication, International government publication: Document Type: Book: All Authors / Contributors: International Atomic Energy Agency. ISBN: X OCLC Number. Get this from a library! Design of the reactor coolant system and associated system nuclear power plants: Safety guide. [International Atomic Energy Agency.;] -- This publication is a revision and combination of two previous safety guides: Safety series No. SG-D6, Ultimate heat sink and directly associated heat transport systems for nuclear power plants. Nuclear reactor - Nuclear reactor - Coolant system: The function of a power reactor installation is to extract as much heat of nuclear fission as possible and convert it to useful power, generally electricity. The coolant system plays a pivotal role in performing this function. A coolant fluid enters the core at low temperature and exits at a higher temperature after collecting the fission energy. – This course is offered to students pursuing non-nuclear majors as a part of the Nuclear Power Engineering Technology Certificate program. – Boiling Water Reactor (BWR) Systems: the systems unique to the BWR for control of the fission process and the .

Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants (IAEA Safety Standards Series) on *FREE* shipping on qualifying offers. Water as a reactor coolant. Water and steam are a common fluid used for heat exchange in the primary circuit (from surface of fuel rods to the coolant flow) and in the secondary circuit. It used due to its availability and high heat capacity, both for cooling and heating. It is especially effective to transport heat through vaporization and condensation of water because of its very large. Reactor protection system (RPS) A reactor protection system is designed to immediately terminate the nuclear reaction. By breaking the nuclear chain reaction, the source of heat is systems can then be used to remove decay heat from the core. All nuclear plants have some form of reactor protection system. Standards Series No. NS-G, Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants, and supersedes it. OBJECTIVE The purpose of this Safety Guide is to provide recommendations and guidance to regulatory bodies, nuclear File Size: 1MB.

R.H.S. WINTERTON, in Thermal Design of Nuclear Reactors, Publisher Summary. This chapter describes the main reactor systems and focuses on those reactor types that are either currently in use for power production or are likely to be brought into use in the near future. The pressurized water reactor (PWR) uses ordinary water as both moderator and coolant. Abstract. This standard addresses the design bases for light water reactor, nuclear power plant structures and components essential for the protection of public health and safety from the potential adverse effects of pipe whip, jet impingement, pressurization of compartments outside containment, environmental conditions and flooding associated with a postulated pipe rupture. Water. Almost all currently operating nuclear power plants are light water reactors using ordinary water under high pressure as coolant and neutron 1/3 are boiling water reactors where the primary coolant undergoes phase transition to steam inside the reactor. About 2/3 are pressurized water reactors at even higher pressure. Current reactors stay under the critical point at.   British Electricity International, in Nuclear Power Generation (Third Edition), Loss of coolant accidents. Loss of coolant accidents (LOCAs) which are analysed, range from very small leaks from the reactor coolant system boundary to the complete severance of the largest pipe (discharge area approximately 1 m 2) in the primary coolant recirculation loop.