Aydin karahan (14 risultati)

Condizione: New.

Paperback. Condizione: Brand New. 148 pages. 8.66x5.91x0.34 inches. In Stock.

Taschenbuch. Condizione: Neu. Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors | Fuel Engineering And Structural analysis Tool (FEAST) | Aydin Karahan (u. a.) | Taschenbuch | 348 S. | Englisch | 2010 | LAP LAMBERT Academic Publishing | EAN 9783838332772 | Verantwortliche Person für die EU: BoD - Books on Demand, In de Tarpen 42, 22848 Norderstedt, info[at]bod[dot]de | Anbieter: preigu.…

Paperback. Condizione: Brand New. 148 pages. 8.66x5.91x0.34 inches. In Stock.

Paperback. Condizione: Brand New. 348 pages. 8.66x5.91x0.79 inches. In Stock.

Taschenbuch. Condizione: Neu. This item is printed on demand - it takes 3-4 days longer - Neuware -The capital cost of a typical BWR is of the order of 65 % of the total power cost, extracting more energy from an existing reactor or reducing the physical size of future BWRs may reduce total cost of nuclear power considerably. The large assembly concept is based on replacing four traditional BWR assemblies and large water gap regions with a single large assembly. Water rods within the assembly maintain the moderating power and accommodate finger type control rods. The new assembly design adopts smaller fuel pins and larger pitch to diameter ratio to allow for the margin to increase the core power density. The originality of the design mainly lies in the use of the dispersed finger-type control rods, which are much more effective compared to the traditional cruciform control rods; as such, the volume of the absorbing material in the assembly can be reduced while satisfying the required rod worth, or shutdown reactivity margin. This feature allows for an increase in pitch-to-diameter ratio without increasing the magnitude of the void coefficient significantly. 148 pp. Englisch.…

Condizione: New. Dieser Artikel ist ein Print on Demand Artikel und wird nach Ihrer Bestellung fuer Sie gedruckt. Autor/Autorin: KARAHAN AYDINAydin Karahan is a Research Scientist at Massachusetts Institute of Technology. He has extensive experience in modeling, simulation and optimization of the nuclear fission reactors. Dr. Karahan s current interest is the.…

Taschenbuch. Condizione: Neu. This item is printed on demand - it takes 3-4 days longer - Neuware -Nuclear fuel behavior modeling is an important piece of optimizing nuclear reactors. The first barrier against release of the radioactivity is the cladding material. A reliable tool is needed to assess the failure margin of this barrier during normal operation as well as accidental situations. To do it, a detailed micro-structural evolution of the fuel and the cladding, mechanical and chemical interaction between the fuel and cladding and the pressurization of the free volume of the fuel pin need to be modeled. The book presents an integrated model including fuel swelling, fission gas release, fuel constituent redistribution, cladding corrosion, straining and fracture for Sodium Fast Reactors. 348 pp. Englisch.…

Condizione: New. Dieser Artikel ist ein Print on Demand Artikel und wird nach Ihrer Bestellung fuer Sie gedruckt. Autor/Autorin: KARAHAN AYDINAydin Karahan is a Research Scientist at Massachusetts Institute of Technology. He has extensive experience in modeling, simulation and optimization of the nuclear fission reactors. Dr. Karahan s current interest is the.…

Taschenbuch. Condizione: Neu. nach der Bestellung gedruckt Neuware - Printed after ordering - Nuclear fuel behavior modeling is an important piece of optimizing nuclear reactors. The first barrier against release of the radioactivity is the cladding material. A reliable tool is needed to assess the failure margin of this barrier during normal operation as well as accidental situations. To do it, a detailed micro-structural evolution of the fuel and the cladding, mechanical and chemical interaction between the fuel and cladding and the pressurization of the free volume of the fuel pin need to be modeled. The book presents an integrated model including fuel swelling, fission gas release, fuel constituent redistribution, cladding corrosion, straining and fracture for Sodium Fast Reactors.…

Taschenbuch. Condizione: Neu. This item is printed on demand - Print on Demand Titel. Neuware -The capital cost of a typical BWR is of the order of 65 % of the total power cost, extracting more energy from an existing reactor or reducing the physical size of future BWRs may reduce total cost of nuclear power considerably. The large assembly concept is based on replacing four traditional BWR assemblies and large water gap regions with a single large assembly. Water rods within the assembly maintain the moderating power and accommodate finger type control rods. The new assembly design adopts smaller fuel pins and larger pitch to diameter ratio to allow for the margin to increase the core power density. The originality of the design mainly lies in the use of the dispersed finger-type control rods, which are much more effective compared to the traditional cruciform control rods; as such, the volume of the absorbing material in the assembly can be reduced while satisfying the required rod worth, or shutdown reactivity margin. This feature allows for an increase in pitch-to-diameter ratio without increasing the magnitude of the void coefficient significantly.VDM Verlag, Dudweiler Landstraße 99, 66123 Saarbrücken 148 pp. Englisch.…

Condizione: New. Print on Demand.

Taschenbuch. Condizione: Neu. This item is printed on demand - Print on Demand Titel. Neuware -Nuclear fuel behavior modeling is an important piece of optimizing nuclear reactors. The first barrier against release of the radioactivity is the cladding material. A reliable tool is needed to assess the failure margin of this barrier during normal operation as well as accidental situations. To do it, a detailed micro-structural evolution of the fuel and the cladding, mechanical and chemical interaction between the fuel and cladding and the pressurization of the free volume of the fuel pin need to be modeled. The book presents an integrated model including fuel swelling, fission gas release, fuel constituent redistribution, cladding corrosion, straining and fracture for Sodium Fast Reactors.VDM Verlag, Dudweiler Landstraße 99, 66123 Saarbrücken 348 pp. Englisch.…

Condizione: New. PRINT ON DEMAND.