LEADER 00000cam a22008897i 4500 001 891381822 003 OCoLC 005 20240129213017.0 006 m o d 007 cr cn||||||||| 008 140912t20152015enkaf ob 001 0 eng d 019 890444932|a896187370|a899157534|a903633134|a990528426 |a1105178221|a1105565234|a1227643815|a1229062430 |a1229062726|a1235118477|a1235832415|a1240509670 020 9780857096470|q(e-book) 020 0857096478|q(e-book) 020 1322097682 020 9781322097688 020 0081013906 020 9780081013908 020 |q(hbk.) 029 1 AU@|b000056016061 029 1 CHNEW|b001012434 029 1 DEBBG|bBV043216146 029 1 DEBSZ|b431888167 029 1 DEBSZ|b43413936X 029 1 GBVCP|b817080333 029 1 GBVCP|b825918855 035 (OCoLC)891381822|z(OCoLC)890444932|z(OCoLC)896187370 |z(OCoLC)899157534|z(OCoLC)903633134|z(OCoLC)990528426 |z(OCoLC)1105178221|z(OCoLC)1105565234|z(OCoLC)1227643815 |z(OCoLC)1229062430|z(OCoLC)1229062726|z(OCoLC)1235118477 |z(OCoLC)1235832415|z(OCoLC)1240509670 037 641019|bMIL 040 E7B|beng|erda|epn|cE7B|dOCLCO|dUIU|dVRC|dOCLCF|dZCU|dYDXCP |dEBLCP|dDEBSZ|dVLB|dB24X7|dOCLCQ|dOCLCO|dCOO|dIDEBK|dCDX |dN$T|dKNOVL|dREB|dOCLCQ|dVT2|dOCLCQ|dK6U|dU3W|dD6H|dCEF |dRRP|dOCLCQ|dLQU|dS9I|dOCLCQ|dORE|dOCLCO|dHS0|dREDDC|dUAB |dOCL|dOCLCO|dUX1|dOCLCO|dOCLCQ|dOCLCO 049 INap 082 04 621.48/332 082 04 621.483|223 082 04 621.48/332|223 099 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 938 Books 24x7|bB247|nbke00078769 938 Coutts Information Services|bCOUT|n29748409 938 ProQuest Ebook Central|bEBLB|nEBL1903773 938 ebrary|bEBRY|nebr10927426 938 EBSCOhost|bEBSC|n839737 938 ProQuest MyiLibrary Digital eBook Collection|bIDEB |ncis29748409 938 YBP Library Services|bYANK|n12065355 994 92|bJFN