Nuclear reactor thermal-hydraulics: past, present and future:
This monograph summarizes the major developments on nuclear reactor thermal-hydraulics over the last fifty years, primarily for the water-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR, and Generation...
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| Main Author: | |
|---|---|
| Format: | Electronic eBook |
| Language: | English |
| Published: |
New York, N.Y.
The American Society of Mechanical Engineers
[2017]
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| Subjects: | |
| Online Access: | Volltext |
| Summary: | This monograph summarizes the major developments on nuclear reactor thermal-hydraulics over the last fifty years, primarily for the water-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR, and Generation IV reactors. This includes discussion on the steady-state reactor thermal hydraulics including subchannel analysis, evolution of emergency core cooling systems (ECCS) from active to fully passive systems to remove the decay heat, and development and consolidation of the best-estimate safety analysis methodology. With substantial increase in computing power, the computational fluid dynamics (CFD) tools for single-phase and multi-phase flows are being used more these days to address some of the important reactor thermal-hydraulics phenomena which could not be analyzed earlier using the traditional one-dimensional or coarse three-dimensional analysis tools. Development of multi-physics methodology encompassing neutronics, thermal-hydraulics, thermal-mechanical and coolant chemistry has also started |
| Item Description: | Includes bibliographical references and index Front Matter -- 1. Introduction -- 2. Steady State Reactor Thermal Hydraulics -- 3. Nuclear Reactor Safety Systems -- 4. Nuclear Reactor Safety Analysis -- 5. Summary and Conclusions -- Back Matter. - System requirements: Adobe Acrobat Reader. - Mode of access: Internet via World Wide Web |
| Physical Description: | 1 Online-Ressource (158 Seiten) Illustrationen |
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| spelling | Saha, P.YYq (Pradip) aut Nuclear reactor thermal-hydraulics: past, present and future Pradip Saha New York, N.Y. The American Society of Mechanical Engineers [2017] 1 Online-Ressource (158 Seiten) Illustrationen txt rdacontent c rdamedia cr rdacarrier Includes bibliographical references and index Front Matter -- 1. Introduction -- 2. Steady State Reactor Thermal Hydraulics -- 3. Nuclear Reactor Safety Systems -- 4. Nuclear Reactor Safety Analysis -- 5. Summary and Conclusions -- Back Matter. - System requirements: Adobe Acrobat Reader. - Mode of access: Internet via World Wide Web This monograph summarizes the major developments on nuclear reactor thermal-hydraulics over the last fifty years, primarily for the water-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR, and Generation IV reactors. This includes discussion on the steady-state reactor thermal hydraulics including subchannel analysis, evolution of emergency core cooling systems (ECCS) from active to fully passive systems to remove the decay heat, and development and consolidation of the best-estimate safety analysis methodology. With substantial increase in computing power, the computational fluid dynamics (CFD) tools for single-phase and multi-phase flows are being used more these days to address some of the important reactor thermal-hydraulics phenomena which could not be analyzed earlier using the traditional one-dimensional or coarse three-dimensional analysis tools. Development of multi-physics methodology encompassing neutronics, thermal-hydraulics, thermal-mechanical and coolant chemistry has also started Nuclear reactors / Cooling Nuclear reactors / Fluid dynamics Nuclear reactors / Safety measures Nuclear reactors / Thermodynamics Thermal hydraulics Kernreaktor (DE-588)4030344-5 gnd rswk-swf Thermohydraulik (DE-588)4470583-9 gnd rswk-swf Electronic books Kernreaktor (DE-588)4030344-5 s Thermohydraulik (DE-588)4470583-9 s DE-604 American Society of Mechanical Engineers Sonstige (DE-588)861-8 oth Erscheint auch als Druck-Ausgabe 9780791861288 https://asmedigitalcollection.asme.org/ebooks/book/36/Nuclear-Reactor-Thermal-Hydraulics-Past-Present Verlag URL des Erstveröffentlichers Volltext |
| spellingShingle | Saha, P.YYq (Pradip) Nuclear reactor thermal-hydraulics: past, present and future Nuclear reactors / Cooling Nuclear reactors / Fluid dynamics Nuclear reactors / Safety measures Nuclear reactors / Thermodynamics Thermal hydraulics Kernreaktor (DE-588)4030344-5 gnd Thermohydraulik (DE-588)4470583-9 gnd |
| subject_GND | (DE-588)4030344-5 (DE-588)4470583-9 |
| title | Nuclear reactor thermal-hydraulics: past, present and future |
| title_auth | Nuclear reactor thermal-hydraulics: past, present and future |
| title_exact_search | Nuclear reactor thermal-hydraulics: past, present and future |
| title_exact_search_txtP | Nuclear reactor thermal-hydraulics: past, present and future |
| title_full | Nuclear reactor thermal-hydraulics: past, present and future Pradip Saha |
| title_fullStr | Nuclear reactor thermal-hydraulics: past, present and future Pradip Saha |
| title_full_unstemmed | Nuclear reactor thermal-hydraulics: past, present and future Pradip Saha |
| title_short | Nuclear reactor thermal-hydraulics: past, present and future |
| title_sort | nuclear reactor thermal hydraulics past present and future |
| topic | Nuclear reactors / Cooling Nuclear reactors / Fluid dynamics Nuclear reactors / Safety measures Nuclear reactors / Thermodynamics Thermal hydraulics Kernreaktor (DE-588)4030344-5 gnd Thermohydraulik (DE-588)4470583-9 gnd |
| topic_facet | Nuclear reactors / Cooling Nuclear reactors / Fluid dynamics Nuclear reactors / Safety measures Nuclear reactors / Thermodynamics Thermal hydraulics Kernreaktor Thermohydraulik |
| url | https://asmedigitalcollection.asme.org/ebooks/book/36/Nuclear-Reactor-Thermal-Hydraulics-Past-Present |
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