Nuclear Reactor Systems : a Technical, Historical and Dynamic Approach.

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The evolution of nuclear reactors since the 1942 Fermi experiment can be described along the lines of natural history, with an initial flourish of uninhibited creativity followed by a severe selection process leading to a handful of surviving species, with light water reactors occupying most of the...

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor principal: Barré, Bertrand
Otros Autores: Anzieu, Pascal, Lenain, Richarch, Thomas, Jean-Baptiste
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Les Ulis : EDP Sciences, 2016.
Colección:Génie Atomique Ser.
Temas:
Nuclear reactors.
Nuclear Reactors
Réacteurs nucléaires.
nuclear reactors.
TECHNOLOGY & ENGINEERING > Mechanical.
Nuclear reactors
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Introduction to the Nuclear Engineering books series ; Authors; Contents; Foreword; References; Chapter 1. Introduction; 1.1. General introduction; 1.2. The ebullient beginnings; 1.2.1. Prehistory [1-10]; 1.2.2. Uranium enrichment, the deus ex machina; 1.3. Bases for comparison [12, 13]; 1.3.1. Fertile and fissile isotopes; 1.3.2. Moderators; 1.3.3. Coolants; 1.4. The driving forces of selection; 1.5. Today (and tomorrow); 1.5.1. Gas-cooled reactors; 1.5.2. Graphite-moderated and boiling water-cooled reactors RBMK; 1.5.3. Heavy water reactors CANDU.
  • 1.5.4. Light water reactors PWR, BWR and VVER1.5.5. High temperature reactors; 1.5.6. Fast breeders [14]; 1.5.7. Molten salt reactors [1]; 1.6. Biotope, domination and selection; 1.7. From spontaneous selection to a formalized process [14, 15]; 1.7.1. GIF, the Generation IV International Forum; 1.7.2. INPRO, International Project on Innovative Nuclear Reactors & Fuel Cycles; 1.8. Fusion; 1.9. Conclusion; References; Chapter 2. CO2 gas cooled reactors; 2.1. Introduction; 2.2. General architecture; 2.3. General features of graphite-moderated reactors.
  • 2.3.1. Fuel: natural uranium and magnesium clad (UNGG & Magnox)2.3.2. Graphite moderator; 2.3.3. General physical properties of graphite moderated reactors; 2.4. UNGG; 2.4.1. The French UNGG program; 2.4.2. St Laurent A example; Caisson; Core; 2.5. Magnox; 2.6. Advanced gas cooled reactor AGR; Reference; Chapter 3. RBMK (Reactor Bolchoi Mochtnosti Kanali); 3.1. General; 3.2. General description; Overall design; Cooling; Core; 3.3. Core physics; Principle of RBMK core design; Void and density effects; Instabilities; Analysis of initial RBMK control rod design.
  • Cavity overpressure protection system3.4. Chernobyl accident; Scenario; Accident sequence and analysis; Initial conditions; 3.5. Changes made to improve RBMK core behavior; References; Chapter 4. Heavy water moderated nuclear reactors; 4.1. Introduction; 4.2. General; 4.2.1. Heavy-water; 4.2.2. Natural uranium; 4.2.3. Pressure tubes; 4.3. Description of a CANDU 6; 4.3.1. Reactor; 4.3.2. Primary system; 4.3.3. Moderator system; 4.3.4. Fuel; 4.3.5. Reactivity control systems; 4.3.6. Safety systems; 4.3.7. Fuel cycle; 4.3.8. The vacuum building.
  • 4.3.9. Difficulties and incidents in the Canadian programme4.3.10. Economy; 4.4. Fuel cycle possibilities; 4.4.1. CANFLEX fuel; 4.4.2. Slightly enriched uranium; 4.4.3. Recycling of the LWR fuel; 4.4.4. Perspectives; References; Appendix 1: Heavy-water production; Appendix 2: A Heavy-water reactor with a reactor pressure vessel; Chapter 5. Nuclear marine propulsion; 5.1. Introduction; 5.2. Main properties required for propulsion; Electricity production on land-based reactors; Navy Applications; 5.3. History and development; USA; USSR; UK; FRANCE; China; 5.4. Naval reactor development [2].

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