Thermal-hydraulic analysis of nuclear reactors:
Saved in:
| Main Author: | |
|---|---|
| Format: | Electronic eBook |
| Language: | English |
| Published: |
Cham [u.a.]
Springer
2015
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| Subjects: | |
| Online Access: | BHS01 BTU01 FAB01 FAW01 FHA01 FHI01 FHN01 FHR01 FKE01 FRO01 FWS01 FWS02 UBY01 Volltext Inhaltsverzeichnis Abstract |
| Physical Description: | 1 Online-Ressource |
| ISBN: | 9783319174341 |
| DOI: | 10.1007/978-3-319-17434-1 |
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Record in the Search Index
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| adam_text | THERMAL-HYDRAULIC ANALYSIS OF NUCLEAR REACTORS
/ ZOHURI, BAHMAN
: 2015
TABLE OF CONTENTS / INHALTSVERZEICHNIS
AN INTRODUCTION TO THERMAL HYDRAULIC ASPECTS OF NUCLEAR POWER REACTORS
THERMODYNAMICS
TRANSPORT PROPERTIES
GENERAL CONSERVATION EQUATIONS
LAMINAR INCOMPRESSIBLE FORCED CONVECTION
TURBULENT FORCED CONVECTION
COMPRESSIBLE FLOW
CONDUCTION HEAT TRANSFER
FORCED CONVECTION HEAT TRANSFER
NATURAL OR FREE CONVECTION
MASS TRANSFER
THERMAL RADIATION
MULTI-PHASE FLOW DYNAMICS
CONVECTIVE BOILING
THERMAL STRESS
HEAT EXCHANGERS
ANALYSIS OF REACTOR ACCIDENT
PROBABILISTIC RISK ASSESSMENT
NUCLEAR POWER PLANTS
NUCLEAR FUEL CYCLE
THE ECONOMIC FUTURE OF NUCLEAR POWER
SAFETY, WASTE DISPOSAL, CONTAINMENT, AND ACCIDENTS
APPENDIX A: TABLE AND GRAPHS COMPILATIONS
APPENDIX B: PHYSICAL PROPERTY TABLES
APPENDIX C: UNITS, DIMENSIONS AND CONVERSION FACTORS
APPENDIX D: PHYSICAL PROPERTIES
APPENDIX E: FLUID PROPERTY DATA
APPENDIX F: BASIC EQUATIONS
DIESES SCHRIFTSTUECK WURDE MASCHINELL ERZEUGT.
THERMAL-HYDRAULIC ANALYSIS OF NUCLEAR REACTORS
/ ZOHURI, BAHMAN
: 2015
ABSTRACT / INHALTSTEXT
THIS TEXT COVERS THE FUNDAMENTALS OF THERMODYNAMICS REQUIRED TO
UNDERSTAND ELECTRICAL POWER GENERATION SYSTEMS AND THE APPLICATION OF
THESE PRINCIPLES TO NUCLEAR REACTOR POWER PLANT SYSTEMS. IT IS NOT
ATRADITIONAL GENERALTHERMODYNAMICS TEXT, PER SE, BUT A PRACTICAL
THERMODYNAMICS VOLUME INTENDED TO EXPLAIN THE FUNDAMENTALS AND APPLY
THEM TO THE CHALLENGES FACING ACTUAL NUCLEAR POWER PLANTS SYSTEMS, WHERE
THERMAL HYDRAULICS COMES TO PLAY. WRITTEN IN A LUCID, STRAIGHT-FORWARD
STYLE WHILE RETAINING SCIENTIFIC RIGOR, THE CONTENT IS ACCESSIBLE TO
UPPER DIVISION UNDERGRADUATE STUDENTS AND AIMED AT PRACTICING ENGINEERS
IN NUCLEAR POWER FACILITIES AND ENGINEERING SCIENTISTS AND TECHNICIANS
IN INDUSTRY, ACADEMIC RESEARCH GROUPS, AND NATIONAL LABORATORIES. THE
BOOK IS ALSO A VALUABLE RESOURCE FOR STUDENTS AND FACULTY IN VARIOUS
ENGINEERING PROGRAMS CONCERNED WITH NUCLEAR REACTORS. THIS BOOK ALSO:
PROVIDES EXTENSIVE COVERAGE OF THERMAL HYDRAULICS WITH THERMODYNAMICS IN
NUCLEAR REACTORS, BEGINNING WITH FUNDAMENTAL DEFINITIONS OF UNITS AND
DIMENSIONS, THERMODYNAMIC VARIABLES, AND THE LAWS OF THERMODYNAMICS
PROGRESSING TO SECTIONS ON SPECIFIC APPLICATIONS OF THE BRAYTON AND
RANKINE CYCLES FOR POWER GENERATION AND PROJECTED REACTOR SYSTEMS DESIGN
ISSUES REINFORCES FUNDAMENTALS OF FLUID DYNAMICS AND HEAT TRANSFER;
THERMAL AND HYDRAULIC ANALYSIS OF NUCLEAR REACTORS, TWO-PHASE FLOW AND
BOILING, COMPRESSIBLE FLOW, STRESS ANALYSIS, AND ENERGY CONVERSION
METHODS INCLUDES DETAILED APPENDICES THAT COVER METRIC AND ENGLISH
SYSTEM UNITS AND CONVERSIONS, DETAILED STEAM AND GAS TABLES, HEAT
TRANSFER PROPERTIES, AND NUCLEAR REACTOR SYSTEM DESCRIPTIONS
DIESES SCHRIFTSTUECK WURDE MASCHINELL ERZEUGT.
|
| any_adam_object | 1 |
| author | Zohuri, Bahman |
| author_facet | Zohuri, Bahman |
| author_role | aut |
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| author_variant | b z bz |
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| dewey-full | 621.4021 |
| dewey-hundreds | 600 - Technology (Applied sciences) |
| dewey-ones | 621 - Applied physics |
| dewey-raw | 621.4021 |
| dewey-search | 621.4021 |
| dewey-sort | 3621.4021 |
| dewey-tens | 620 - Engineering and allied operations |
| discipline | Energietechnik |
| doi_str_mv | 10.1007/978-3-319-17434-1 |
| format | Electronic eBook |
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| language | English |
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| spellingShingle | Zohuri, Bahman Thermal-hydraulic analysis of nuclear reactors Engineering Applied mathematics Engineering mathematics Thermodynamics Heat engineering Heat transfer Mass transfer Fluid mechanics Nuclear engineering Engineering Thermodynamics, Heat and Mass Transfer Appl.Mathematics/Computational Methods of Engineering Engineering Fluid Dynamics Nuclear Engineering Ingenieurwissenschaften |
| title | Thermal-hydraulic analysis of nuclear reactors |
| title_auth | Thermal-hydraulic analysis of nuclear reactors |
| title_exact_search | Thermal-hydraulic analysis of nuclear reactors |
| title_full | Thermal-hydraulic analysis of nuclear reactors Bahman Zohuri ; Nima Fathi |
| title_fullStr | Thermal-hydraulic analysis of nuclear reactors Bahman Zohuri ; Nima Fathi |
| title_full_unstemmed | Thermal-hydraulic analysis of nuclear reactors Bahman Zohuri ; Nima Fathi |
| title_short | Thermal-hydraulic analysis of nuclear reactors |
| title_sort | thermal hydraulic analysis of nuclear reactors |
| topic | Engineering Applied mathematics Engineering mathematics Thermodynamics Heat engineering Heat transfer Mass transfer Fluid mechanics Nuclear engineering Engineering Thermodynamics, Heat and Mass Transfer Appl.Mathematics/Computational Methods of Engineering Engineering Fluid Dynamics Nuclear Engineering Ingenieurwissenschaften |
| topic_facet | Engineering Applied mathematics Engineering mathematics Thermodynamics Heat engineering Heat transfer Mass transfer Fluid mechanics Nuclear engineering Engineering Thermodynamics, Heat and Mass Transfer Appl.Mathematics/Computational Methods of Engineering Engineering Fluid Dynamics Nuclear Engineering Ingenieurwissenschaften |
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