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Nuclear reactor / / R. K. Singal
| Nuclear reactor / / R. K. Singal |
| Autore | Singal R. K. |
| Pubbl/distr/stampa | Daryaganj, New Delhi, India : , : New Age International (P) Ltd., Publishers, , 2015 |
| Descrizione fisica | 1 online resource (209 pages) |
| Disciplina | 621.4832 |
| Soggetto topico |
Nuclear reactors
Nuclear physics |
| Soggetto genere / forma | Electronic books. |
| ISBN | 81-224-3909-8 |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910466387803321 |
Singal R. K.
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| Daryaganj, New Delhi, India : , : New Age International (P) Ltd., Publishers, , 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Nuclear reactor / / R. K. Singal
| Nuclear reactor / / R. K. Singal |
| Autore | Singal R. K. |
| Pubbl/distr/stampa | Daryaganj, New Delhi, India : , : New Age International (P) Ltd., Publishers, , 2015 |
| Descrizione fisica | 1 online resource (209 pages) |
| Disciplina | 621.4832 |
| Soggetto topico |
Nuclear reactors
Nuclear physics |
| ISBN | 81-224-3909-8 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910796484903321 |
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Singal R. K.
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| Daryaganj, New Delhi, India : , : New Age International (P) Ltd., Publishers, , 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Nuclear reactor / / R. K. Singal
| Nuclear reactor / / R. K. Singal |
| Autore | Singal R. K. |
| Pubbl/distr/stampa | Daryaganj, New Delhi, India : , : New Age International (P) Ltd., Publishers, , 2015 |
| Descrizione fisica | 1 online resource (209 pages) |
| Disciplina | 621.4832 |
| Soggetto topico |
Nuclear reactors
Nuclear physics |
| ISBN | 81-224-3909-8 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910814980903321 |
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Singal R. K.
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| Daryaganj, New Delhi, India : , : New Age International (P) Ltd., Publishers, , 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Nuclear reactor analysis / James J. Duderstadt, Louis J. Hamilton
| Nuclear reactor analysis / James J. Duderstadt, Louis J. Hamilton |
| Autore | Duderstadt, James J. <1942- > |
| Pubbl/distr/stampa |
< |
| Descrizione fisica | XVII, 650 p. ; 25 cm. |
| Disciplina | 621.4832 |
| Altri autori (Persone) | Hamilton, Louis J. <1941- > |
| Soggetto topico |
Reattori nucleari
Ingegneria nucleare |
| ISBN | 0-471-22363-8 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNIBAS-000028100 |
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Duderstadt, James J. <1942- >
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| <<John>> Wiley, 1976 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. della Basilicata | ||
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Nuclear Reactor Design / / edited by Yoshiaki Oka
| Nuclear Reactor Design / / edited by Yoshiaki Oka |
| Edizione | [1st ed. 2014.] |
| Pubbl/distr/stampa | Tokyo : , : Springer Japan : , : Imprint : Springer, , 2014 |
| Descrizione fisica | 1 online resource (337 p.) |
| Disciplina |
621.48
621.4832 |
| Collana | An Advanced Course in Nuclear Engineering |
| Soggetto topico |
Nuclear energy
Energy systems Nuclear chemistry Engineering design Nuclear Energy Energy Systems Nuclear Chemistry Engineering Design |
| ISBN | 4-431-54898-X |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Fuel Burnup and Reactivity Control -- Nuclear Reactor Calculations -- Core Design of Light Water Reactors -- Core Design of Advanced Reactors. |
| Record Nr. | UNINA-9910299749103321 |
| Tokyo : , : Springer Japan : , : Imprint : Springer, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Preparation of radiological effluent technical specification for nuclear power plants : a guidance manual for users of standard technical specifications / / editors, J.S. Boegli [and fifteen others]
| Preparation of radiological effluent technical specification for nuclear power plants : a guidance manual for users of standard technical specifications / / editors, J.S. Boegli [and fifteen others] |
| Pubbl/distr/stampa | Washington, D.C. : , : Division of Site Safety and Environmental Analysis, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission, , 1987 |
| Descrizione fisica | 1 online resource (various pagings) |
| Disciplina | 621.4832 |
| Soggetto topico |
Radioactive pollution of the atmosphere - Mathematical models
Water cooled reactors Nuclear engineering - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Preparation of radiological effluent technical specification for nuclear power plants |
| Record Nr. | UNINA-9910707679203321 |
| Washington, D.C. : , : Division of Site Safety and Environmental Analysis, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission, , 1987 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Seismic design criteria for structures, systems, and components in nuclear facilities / / American Society of Civil Engineers
| Seismic design criteria for structures, systems, and components in nuclear facilities / / American Society of Civil Engineers |
| Pubbl/distr/stampa | Reston, Virginia : , : American Society of Civil Engineers, , [2019] |
| Descrizione fisica | 1 online resource (107 pages) : illustrations |
| Disciplina | 621.4832 |
| Collana | ASCE standard |
| Soggetto topico | Nuclear power plants - Earthquake effects |
| Soggetto genere / forma | Electronic books. |
| ISBN | 0-7844-8240-3 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910449761803321 |
| Reston, Virginia : , : American Society of Civil Engineers, , [2019] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thermal Design of Nuclear Reactors
| Thermal Design of Nuclear Reactors |
| Autore | Winterton R. H. S |
| Pubbl/distr/stampa | Burlington, : Elsevier Science, 1981 |
| Descrizione fisica | 1 online resource (415 p.) |
| Disciplina |
621.48/32
621.4832 |
| Collana | Pergamon international library of science, technology, engineering, and social studies Thermal design of nuclear reactors |
| Soggetto topico |
Nuclear reactors -- Design and construction
Nuclear reactors - Design and construction Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 1-4831-4524-7 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Cover image; Title page; Table of Contents; Other Titles of Interest; Copyright; Preface; Chapter 1: Summary of Reactor Physics; Publisher Summary; INTRODUCTION; FISSION; NEUTRON FLUX AND REACTION CROSS-SECTIONS; CRITICALITY; MODERATORS; BREEDING; THE MULTIPLICATION CONSTANT; NEUTRON FLUX DISTRIBUTION; PRACTICAL REACTOR SYSTEMS; SUMMARY; Chapter 2: Reactor Systems; Publisher Summary; INTRODUCTION; THE PRESSURIZED WATER REACTOR; THE BOILING WATER REACTOR; THE GAS-COOLED REACTOR-THE AGR; THE SODIUM-COOLED FAST BREEDER REACTOR; Chapter 3: Fuel-Rod Design; Publisher Summary; INTRODUCTION
TEMPERATURE DISTRIBUTION IN A CYLINDRICAL FUEL PELLETAllowance for variations in conductivity and heat generation; Effect of porosity on UO2 thermal conductivity; Measurements of UO2 thermal conductivity; HEAT TRANSFER IN THE GAP BETWEEN FUEL AND CLADDING; HEAT TRANSFER THROUGH CYLINDRICAL CLADDING; FISSION GAS RELEASE; DETAILS OF FUEL ROD CONSTRUCTION; Problems; Chapter 4: Forced-Convection Heat Transfer; Publisher Summary; INTRODUCTION; HEAT-TRANSFER COEFFICIENT AND DIMENSIONAL ANALYSIS; HEAT-TRANSFER CORRELATIONS FOR NON-METALS; LIQUID-METAL HEAT TRANSFER; COMPARISON OF COOLANTS IMPROVEMENT OF HEAT TRANSFER USING FINSIMPROVEMENT OF HEAT TRANSFER BY ROUGHENING THE SURFACE; Problems; Chapter 5: Boiling Heat Transfer; Publisher Summary; INTRODUCTION; NUCLEATION; TYPES OF BOILING; FLOW REGIMES IN FORCED-CONVECTION BOILING; Quality, void fraction and slip ratio; HEAT-TRANSFER CORRELATIONS FOR FLOW BOILING; Film boiling; CRITICAL HEAT-FLUX CORRELATIONS FOR FORCED-CONVECTION BOILING OF WATER; Correlations for bulk boiling; Problems; Chapter 6: Fluid Flow; Publisher Summary; INTRODUCTION; PRESSURE DROP WITH A LIQUID COOLANT; PUMPING POWER PRESSURE DROP WITH A GASEOUS COOLANTPRESSURE DROP WITH A TWO-PHASE MIXTURE; CRITICAL FLOW THROUGH BURST PIPES; Problems; Chapter 7: Safety Analysis; Publisher Summary; INTRODUCTION; TIMESCALES OF THE TRANSIENT FLOW AND HEAT-TRANSFER PROCESSES; THE SOURCES OF HEAT; SIMPLE MODEL FOR CLAD TEMPERATURE DURING TRANSIENT; DISCUSSION OF LOSS OF COOLANT ACCIDENTS; THE PROBABILITY APPROACH TO REACTOR SAFETY; THE SODIUM-COOLED FAST REACTOR; Problems; Chapter 8: Core Thermohydraulic Design; Publisher Summary; INTRODUCTION; MAXIMUM CAN TEMPERATURE IN A COOLANT CHANNEL; The maximum fuel temperature MINIMUM CRITICAL HEAT-FLUX RATIOHOT-CHANNEL FACTORS; GAGS; SUBCHANNEL ANALYSIS; INCREASING HEAT OUTPUT IN GAS-COOLED REACTORS; MAXIMISING STEAM PRODUCTION SUBJECT TO FIXED CRITICAL HEAT FLUX RATIO; Problems; Chapter 9: Steam Cycles; Publisher Summary; INTRODUCTION; THE TEMPERATURE-ENTHALPY DIAGRAM; THE BASIC RANKINE CYCLE; FEED WATER HEATING (REGENERATION); PRACTICAL CYCLES FOR WATER REACTORS; PUMPING POWER AND OTHER LOSSES; RADIOACTIVE STEAM IN THE BWR; CYCLES FOR HIGH-TEMPERATURE REACTORS; NET PLANT EFFICIENCY; COMBINED HEAT AND POWER GENERATION; Problems; Chapter 10: Fusion Reactors Publisher Summary |
| Record Nr. | UNINA-9910148607303321 |
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Winterton R. H. S
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| Burlington, : Elsevier Science, 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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