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099    eBook O'Reilly for Public Libraries 
245 00 Irradiation embrittlement of reactor pressure vessels 
       (RPVs) in nuclear power plants /|cedited by Naoki Soneda.
       |h[O'Reilly electronic resource] 
264  1 Cambridge [England] :|bWoodhead Publishing,|c2015. 
264  4 |c©2015 
300    1 online resource (xxii, 409 pages, 4 unnumbered pages of 
       color plates) :|billustrations (some colour) 
336    text|btxt|2rdacontent 
336    still image|bsti|2rdacontent 
337    computer|bc|2rdamedia 
338    online resource|bcr|2rdacarrier 
490 1  Woodhead Publishing series in energy ;|vnumber 26 
504    Includes bibliographical references and index at the end 
       of each chapters. 
505 00 |gMachine generated contents note:|gpt. I|tReactor 
       pressure vessel (RPV) design and fabrication --|g1.
       |tReactor pressure vessel (RPV) design and fabrication: 
       the case of the USA /|rR.K. Nanstad --|g1.1.|tIntroduction
       --|g1.2.|tAmerican Society of Mechanical Engineers (ASME) 
       Code design practices --|g1.3.|tThe design process --
       |g1.4.|tReactor pressure vessel (RPV) materials selection 
       --|g1.5.|tToughness requirements --|g1.6.|tRPV fabrication
       processes --|g1.7.|tWelding practices --|g1.8.|tReferences
       --|g2.|tReactor pressure vessel (RPV) components: 
       processing and properties /|rY. Tanaka --|g2.1.
       |tIntroduction --|g2.2.|tAdvances in nuclear reactor 
       pressure vessel (RPV) components --|g2.3.|tMaterials for 
       nuclear RPVs --|g2.4.|tManufacturing technologies --|g2.5.
       |tMetallurgical and mechanical properties of components --
       |g2.6.|tConclusions --|g2.7.|tReferences --|g3.|tWWER-type
       reactor pressure vessel (RPV) materials and fabrication /
       |rM. Brumovsky --|g3.1.|tIntroduction --|g3.2.|tWWER 
       reactor pressure vessel (RPV) materials --|g3.3.
       |tProduction of materials for components and welding 
       techniques --|g3.4.|tFuture trends --|g3.5.|tSources of 
       further information and advice --|gpt. II|tReactor 
       pressure vessel (RPV) embrittlement in operational nuclear
       power plants --|g4.|tEmbrittlement of reactor pressure 
       vessels (RPVs) in pressurized water reactors (PWRs) /|rP. 
       Todeschini --|g4.1.|tIntroduction --|g4.2.
       |tCharacteristics of pressurized water reactor (PWR) 
       reactor pressure vessel (RPV) embrittlement --|g4.3.|tUS 
       surveillance database --|g4.4.|tFrench surveillance 
       database --|g4.5.|tJapanese surveillance database --|g4.6.
       |tSurveillance databases from other countries --|g4.7.
       |tFuture trends --|g4.8.|tReferences --|g5.|tEmbrittlement
       of reactor pressure vessels (RPVs) in WWER-type reactors /
       |rM. Brumovsky --|g5.1.|tIntroduction --|g5.2.
       |tCharacteristics of embrittlement of WWER reactor 
       pressure vessel (RPV) materials --|g5.3.|tTrend curves --
       |g5.4.|tWWER surveillance programmes --|g5.5.|tRPV 
       annealing in WWER reactors --|g5.6.|tRPV annealing 
       technology --|g5.7.|tSources of further information and 
       advice --|g5.8.|tReferences --|g6.|tIntegrity and 
       embrittlement management of reactor pressure vessels 
       (RPVs) in light-water reactors /|rR.K. Nanstad --|g6.1.
       |tIntroduction --|g6.2.|tParameters governing reactor 
       pressure vessel (RPV) integrity --|g6.3.|tPressure -- 
       temperature operating limits --|g6.4.|tPressurized thermal
       shock (PTS) --|g6.5.|tMitigation methods --|g6.6.
       |tLicensing considerations --|g6.7.|tReferences --|g7.
       |tSurveillance of reactor pressure vessel (RPV) 
       embrittlement in Magnox reactors /|rM.R. Wootton --|g7.1.
       |tIntroduction --|g7.2.|tHistory of Magnox reactors --
       |g7.3.|tReactor pressure vessel (RPV) materials and 
       construction --|g7.4.|tReactor operating rules --|g7.5.
       |tDesign of the surveillance schemes --|g7.6.|tEarly 
       surveillance results --|g7.7.|tDose-damage relationships 
       and intergranular fracture in irradiated submerged-arc 
       welds (SAWs) --|g7.8.|tInfluence of thermal neutrons --
       |g7.9.|tValidation of toughness assessment methodology by 
       RPV SAW sampling --|g7.10.|tFinal remarks --|g7.11.
       |tAcknowledgements --|g7.12.|tReferences --|gpt. III
       |tTechniques for the evaluation of reactor pressure vessel
       (RPV) embrittlement --|g8.|tIrradiation simulation 
       techniques for the study of reactor pressure vessel (RPV) 
       embrittlement /|rK. Fukuya --|g8.1.|tIntroduction --|g8.2.
       |tTest reactor irradiation --|g8.3.|tIon irradiation --
       |g8.4.|tElectron irradiation --|g8.5.|tAdvantages and 
       limitations --|g8.6.|tFuture trends --|g8.7.|tSources of 
       further information and advice --|g8.8.|tReferences --|g9.
       |tMicrostructural characterisation techniques for the 
       study of reactor pressure vessel (RPV) embrittlement /
       |rC.A. English --|g9.1.|tIntroduction --|g9.2.
       |tMicrostructural development and characterisation 
       techniques --|g9.3.|tTransmission electron microscopy 
       (TEM) --|g9.4.|tSmall angle neutron scattering (SANS) --
       |g9.5.|tAtom probe tomography (APT) --|g9.6.|tPositron 
       annihilation spectroscopy (PAS) --|g9.7.|tAuger electron 
       spectroscopy (AES) --|g9.8.|tOther techniques --|g9.9.
       |tUsing microstructural analysis to understand the 
       mechanisms of reactor pressure vessel (RPV) embrittlement 
       --|g9.10.|tGrain boundary segregation --|g9.11.|tMatrix 
       damage --|g9.12.|tSolute clusters --|g9.13.|tMechanistic 
       framework to develop dose-damage relationships (DDRs) --
       |g9.14.|tRecent developments and overall summary --|g9.15.
       |tReferences --|g10.|tEvaluating the fracture toughness of
       reactor pressure vessel (RPV) materials subject to 
       embrittlement /|rM. Brumovsky --|g10.1.|tIntroduction --
       |g10.2.|tThe development of fracture mechanics --|g10.3.
       |tPlane-strain fracture toughness and crack-arrest 
       toughness --|g10.4.|tCurrent standard of fracture 
       toughness curve --|g10.5.|tEffects of irradiation on 
       fracture toughness --|g10.6.|tFracture toughness versus 
       Charpy impact energy --|g10.7.|tHeavy Section Steel 
       Technology Program and other international reactor 
       pressure vessel (RPV) research programs --|g10.8.
       |tAdvantages and limitations of fracture toughness testing
       --|g10.9.|tFuture trends --|g10.10.|tReferences --|g11.
       |tEmbrittlement correlation methods to identify trends in 
       embrittlement in reactor pressure vessels (RPVs) /|rN. 
       Soneda --|g11.1.|tIntroduction --|g11.2.|tDevelopment of 
       the embrittlement correlation method --|g11.3.
       |tEmbrittlement correlation methods: USA --|g11.4.
       |tEmbrittlement correlation methods: Europe --|g11.5.
       |tEmbrittlement correlation methods: Japan --|g11.6.
       |tConclusions --|g11.7.|tReferences --|g12.|tProbabilistic
       fracture mechanics risk analysis of reactor pressure 
       vessel (RPV) integrity /|rR.M. Gamble --|g12.1.
       |tIntroduction --|g12.2.|tRisk evaluation procedures for 
       assessing reactor pressure vessel (RPV) integrity --
       |g12.3.|tProbabilistic fracture mechanics analysis 
       software --|g12.4.|tConditional probability computational 
       procedure --|g12.5.|tExample calculations and applications
       --|g12.6.|tFuture trends --|g12.7.|tReferences. 
520    Reactor Pressure Vessels (RPVs) contain the fuel and 
       therefore the reaction at the heart of nuclear power 
       plants. They are a life-determining structural component: 
       if they suffer serious damage, the continued operation of 
       the plant is in jeopardy. This book critically reviews 
       irradiation embrittlement, the main degradation mechanism 
       affecting RPV steels, and mitigation routes for managing 
       the RPV lifetime. Part I reviews RPV design and 
       fabrication in different countries, with an emphasis on 
       the materials required, their important properties, and 
       manufacturing technologies. Part II then con. 
546    English. 
588 0  Print version record. 
590    O'Reilly|bO'Reilly Online Learning: Academic/Public 
       Library Edition 
650  0 Nuclear pressure vessels|xEffect of radiation on. 
650  0 Steel|xEffect of radiation on. 
650  0 Steel|xEmbrittlement. 
650  0 Nuclear reactors. 
650  2 Nuclear Reactors 
650  6 Réacteurs nucléaires|xCaissons|xEffets du rayonnement sur.
650  6 Acier|xEffets du rayonnement sur. 
650  6 Acier|xFragilisation. 
650  6 Réacteurs nucléaires. 
650  7 nuclear reactors.|2aat 
650  7 Steel|xEmbrittlement|2fast 
650  7 Steel|xEffect of radiation on|2fast 
650  7 Nuclear pressure vessels|xEffect of radiation on|2fast 
650  7 Nuclear pressure vessels|2fast 
650  7 Nuclear reactors|2fast 
700 1  Soneda, Naoki,|eeditor. 
776 08 |iPrint version:|tIrradiation embrittlement of reactor 
       pressure vessels (RPVs) in nuclear power plants.
       |dCambridge, [England] : Woodhead Publishing, ©2015|hxxii,
       409 pages|kWoodhead Publishing in energy ; Number 26
       |z9781845699673 
830  0 Woodhead Publishing in energy ;|vno. 26. 
856 40 |uhttps://ezproxy.naperville-lib.org/login?url=https://
       learning.oreilly.com/library/view/~/9781845699673/?ar
       |zAvailable on O'Reilly for Public Libraries 
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