LEADER 03252nam 2200433 450 001 9910583384303321 005 20230120002521.0 010 $a0-08-100679-9 010 $a0-08-100662-4 035 $a(CKB)3710000001368931 035 $a(MiAaPQ)EBC4863031 035 $a(CaSebORM)9780081006795 035 $a(EXLCZ)993710000001368931 100 $a20170616h20172017 uy 0 101 0 $aeng 135 $aurcnu|||||||| 181 $2rdacontent 182 $2rdamedia 183 $2rdacarrier 200 10$aThermal-hydraulics of water cooled nuclear reactors /$fFrancesco D'Auria 205 $a1st edition 210 1$aLondon, [England] :$cAcademic Press,$d2017. 210 4$dİ2017 215 $a1 online resource (1,121 pages) $cillustrations 320 $aIncludes bibliographical references and index. 330 $aThermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants 606 $aWater cooled reactors 606 $aThermal hydraulics 615 0$aWater cooled reactors. 615 0$aThermal hydraulics. 676 $a539.7213 700 $aD'Auria$b Francesco$0237945 801 0$bMiAaPQ 801 1$bMiAaPQ 801 2$bMiAaPQ 906 $aBOOK 912 $a9910583384303321 996 $aThermal-hydraulics of water cooled nuclear reactors$92163409 997 $aUNINA