Thermo-hydraulics of nuclear reactors:
This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal opera...
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| Format: | Elektronisch E-Book |
| Sprache: | English |
| Veröffentlicht: |
Cambridge
Cambridge University Press
2016
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| Schlagworte: | |
| Online-Zugang: | BSB01 FHN01 URL des Erstveröffentlichers |
| Zusammenfassung: | This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima as well as the major improvements to reactor safety that grew out of those analyses and accidents |
| Beschreibung: | Title from publisher's bibliographic system (viewed on 05 Apr 2016) |
| Beschreibung: | 1 online resource (xv, 155 pages) |
| ISBN: | 9781316494264 |
| DOI: | 10.1017/CBO9781316494264 |
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| 505 | 8 | |a Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents | |
| 520 | |a This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima as well as the major improvements to reactor safety that grew out of those analyses and accidents | ||
| 650 | 4 | |a Nuclear reactors / Fluid dynamics | |
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Datensatz im Suchindex
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| author | Brennen, Christopher E. 1941- |
| author_facet | Brennen, Christopher E. 1941- |
| author_role | aut |
| author_sort | Brennen, Christopher E. 1941- |
| author_variant | c e b ce ceb |
| building | Verbundindex |
| bvnumber | BV043940178 |
| collection | ZDB-20-CBO |
| contents | Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents |
| ctrlnum | (ZDB-20-CBO)CR9781316494264 (OCoLC)967758321 (DE-599)BVBBV043940178 |
| dewey-full | 621.48/3 |
| dewey-hundreds | 600 - Technology (Applied sciences) |
| dewey-ones | 621 - Applied physics |
| dewey-raw | 621.48/3 |
| dewey-search | 621.48/3 |
| dewey-sort | 3621.48 13 |
| dewey-tens | 620 - Engineering and allied operations |
| discipline | Energietechnik |
| doi_str_mv | 10.1017/CBO9781316494264 |
| format | Electronic eBook |
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| id | DE-604.BV043940178 |
| illustrated | Not Illustrated |
| indexdate | 2024-07-10T07:39:12Z |
| institution | BVB |
| isbn | 9781316494264 |
| language | English |
| oai_aleph_id | oai:aleph.bib-bvb.de:BVB01-029349148 |
| oclc_num | 967758321 |
| open_access_boolean | |
| owner | DE-12 DE-92 |
| owner_facet | DE-12 DE-92 |
| physical | 1 online resource (xv, 155 pages) |
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| publishDate | 2016 |
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| publisher | Cambridge University Press |
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| spelling | Brennen, Christopher E. 1941- Verfasser aut Thermo-hydraulics of nuclear reactors Christopher Earls Brennen, California Institute of Technology Pasadena, California Cambridge Cambridge University Press 2016 1 online resource (xv, 155 pages) txt rdacontent c rdamedia cr rdacarrier Title from publisher's bibliographic system (viewed on 05 Apr 2016) Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima as well as the major improvements to reactor safety that grew out of those analyses and accidents Nuclear reactors / Fluid dynamics Nuclear energy Erscheint auch als Druckausgabe 978-1-107-13960-2 https://doi.org/10.1017/CBO9781316494264 Verlag URL des Erstveröffentlichers Volltext |
| spellingShingle | Brennen, Christopher E. 1941- Thermo-hydraulics of nuclear reactors Mathematical nomenclature -- Basic nuclear power generation -- Core neutronics -- Some reactor designs -- Core heat transfer -- Multiphase flow -- Reactor multiphase flows and accidents Nuclear reactors / Fluid dynamics Nuclear energy |
| title | Thermo-hydraulics of nuclear reactors |
| title_auth | Thermo-hydraulics of nuclear reactors |
| title_exact_search | Thermo-hydraulics of nuclear reactors |
| title_full | Thermo-hydraulics of nuclear reactors Christopher Earls Brennen, California Institute of Technology Pasadena, California |
| title_fullStr | Thermo-hydraulics of nuclear reactors Christopher Earls Brennen, California Institute of Technology Pasadena, California |
| title_full_unstemmed | Thermo-hydraulics of nuclear reactors Christopher Earls Brennen, California Institute of Technology Pasadena, California |
| title_short | Thermo-hydraulics of nuclear reactors |
| title_sort | thermo hydraulics of nuclear reactors |
| topic | Nuclear reactors / Fluid dynamics Nuclear energy |
| topic_facet | Nuclear reactors / Fluid dynamics Nuclear energy |
| url | https://doi.org/10.1017/CBO9781316494264 |
| work_keys_str_mv | AT brennenchristophere thermohydraulicsofnuclearreactors |