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Book
Regulatory guide 1.37 : quality assurance requirements for cleaning of fluid systems and associated components of water-cooled nuclear power plants
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Year: 2007 Publisher: [Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,

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Book
The advanced test reactor (ATR)
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Year: 2005 Publisher: [Idaho Falls, Idaho] : Idaho National Laboratory,

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Book
La technologie des réacteurs à eau pressurisée
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ISBN: 2759824179 9782759824175 9782759823604 Year: 2019 Publisher: France

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« La technologie des réacteurs à eau pressurisée » est un ouvrage conçu pour les professionnels du domaine nucléaire, mais qui peut aussi être abordé par des ingénieurs néophytes désirant s’initier. Il propose un panorama très complet de cette filière de réacteurs depuis son origine aux USA à partir des réalisations de moteurs atomiques pour la propulsion navale jusqu’à ses derniers développements dans le domaine de la production civile d’énergie, particulièrement en France avec les 58 réacteurs d’EDF. Les principaux composants d’une tranche nucléaire sont présentés, à savoir les bâtiments de l’ilot nucléaire, le circuit primaire principal, le pressuriseur, les pompes primaires, la cuve et ses internes, le coeur du réacteur et ses barres de contrôle, l’instrumentation, les générateurs de vapeur, le circuit secondaire de vapeur, la turbine et le condenseur, l’alternateur, les transformateurs et l’alimentation électrique, et les aéroréfrigérants. Un chapitre spécifique détaille les circuits les plus importants de la tranche : RCV, RRA, RRI, ARE, ASG, EAS, CVX, CEX, CRF, GCT… L’ouvrage comporte une très riche iconographie en couleurs, ainsi qu’un index et une bibliographie très détaillée qui permettent au lecteur d’approfondir sa compréhension de ce domaine très complexe. L’auteur, Serge Marguet, est un spécialiste reconnu des réacteurs nucléaires. Il a déjà publié de nombreux livres sur la question (prix SFEN 2018 pour son ouvrage sur La physique des réacteurs nucléaires). Il enseigne la physique des réacteurs à l’INSA-Centre-Val de Loire à Bourges ainsi qu’à l’Institut de transfert de technologie d’EDF/R&D et l’Institut national des sciences et techniques nucléaires (INSTN). Il est également expert industriel de l’Institut international de l’énergie nucléaire (I2EN), organisme chargé de promouvoir le nucléaire français à l’international par la formation. Il travaille depuis plus de 30 ans à la R&D d’EDF au développement des grands codes de calcul de physique des réacteurs, et a contribué à l’élaboration des simulateurs et des outils d’aide au pilotage du dernier réacteur mis en service en France : l’EPR.


Book
Regulatory guide 1.37 : quality assurance requirements for cleaning of fluid systems and associated components of water-cooled nuclear power plants
Author:
Year: 2007 Publisher: [Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,

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Book
The advanced test reactor (ATR)
Author:
Year: 2005 Publisher: [Idaho Falls, Idaho] : Idaho National Laboratory,

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Materials and water chemistry for supercritical water-cooled reactors
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ISBN: 9780081020500 0081020503 008102049X 9780081020494 9780081020494 Year: 2018 Publisher: Duxford, Kidlington, England ; Cambridge, Massachusetts : Woodhead Publishing,

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Materials and Water Chemistry for Supercritical Water-cooled Reactors is unique in that it brings together materials and water chemistry, their interrelationship, the historical perspective and their application to SCWR conceptual design. Written by world's leading experts, all active in the area of materials and chemistry R & D in support of GEN IV SCWR, this book presents for the first time a comprehensive reference on these topics, and in particular, how these data relate to the SCWR design itself. This book is an essential text for researchers in the areas of supercritical water-cooled reactor materials and chemistry, working in industry or academia. It will also give newcomers to the field a survey of all of the available literature and a clear understanding of how these studies relate to the design of the SCWR concept. The material presented is at a specialist's level in materials or corrosion science, or in water chemistry of power plants.


Book
Unisolatable reactor system coolant leak following repeated applications of leak sealant.
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Year: 1993 Publisher: Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation,

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Book
Current state of research on pressurized water reactor safety
Authors: ---
Year: 2018 Publisher: [Place of publication not identified] : EDP Sciences,

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For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally. This publication reflects IRSN's desire to keep an enduring record of its results and to share its knowledge.


Book
Preliminary neutronic analysis of a cavity test reactor
Authors: ---
Year: 1973 Publisher: Washington, D.C. : National Aeronautics and Space Administration,

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Book
Current state of research on pressurized water reactor safety
Authors: ---
Year: 2018 Publisher: [Place of publication not identified] : EDP Sciences,

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Abstract

For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally. This publication reflects IRSN's desire to keep an enduring record of its results and to share its knowledge.

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