Sodium Graphite Reactors PDF Download

Author: Chauncey Starr
Publisher:
ISBN:
Category : Sodium graphite reactors
Languages : en
Pages : 312

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Author: B. R. Hayward
Publisher:
ISBN:
Category : Sodium graphite reactors
Languages : en
Pages : 52

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Book Description

Author: H. H. Cappel
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ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages : 60

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Author:
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Category : Nuclear engineering
Languages : en
Pages :

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Category :
Languages : en
Pages :

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Book Description
An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth).

Author: B. R. Hayward
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 40

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Author: T. J. Connolly
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Category : Nuclear reactors
Languages : en
Pages : 32

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Author: Edward F. Weisner
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ISBN:
Category : Sodium graphite reactors
Languages : en
Pages : 60

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Author: Chauncey STARR (and DICKINSON (Robert Winchester))
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ISBN:
Category :
Languages : en
Pages :

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Author:
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Category :
Languages : en
Pages :

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An analysis of the transient behavior of a 255-Mw(e) advanced sodium graphite reactor, previously described in NAA-SR-3829, is presented. The reactor and its components are briefly described. Nuclear and thermal characteristics are presented as far as they affect reactor kinetics or are essential in interpreting the results. The study includes an investigation of the inherent kinetic characteristics of the reactor, as well as and analysis of its transient behavior for all conceivable conditions of abnormal operations. Assumed reactor excursions are analyzed with and without ensuing protective system action. It is shown that the reactor is dynamically stable and that power transients which are followed by normal protective system actions will not lead to potentially unsafe conditions. The conclusion is reached furthermore, that uncontrolled rod withdrawal accidents from source power will be terminated by coolant choking'' and fuel meltdown before extensive coolant boiling occurs, and that the large thermal capacity and long-time constant of the upper plenum will provide protection against pool boiling for other less serious accidents until the reactor can be shut down by external means. (auth).