Download Advances in Nuclear Science and Technology: v. 6 by Ernest J. Henley, Jeffery Lewins PDF

By Ernest J. Henley, Jeffery Lewins

Advances in Nuclear technology and know-how, quantity 6 presents details pertinent to the basic elements of nuclear technology and know-how. This ebook covers numerous themes, together with nuclear steam generator, oscillations, quick reactor gas, fuel centrifuge, thermal delivery method, and gas cycle.

Organized into six chapters, this quantity starts with an outline of the excessive criteria of technical security for Europes first nuclear-propelled service provider send. this article then examines the country of information relating qualitative effects at the habit of the ideas of the nonlinear element kinetics equations with linear suggestions. different chapters examine the mathematical equipment utilized in the calculations and description the most beneficial properties strange to quick platforms. This booklet discusses besides the thermal shipping in reactors. the ultimate bankruptcy bargains with the prestige of nuclear power in Western Europe, which depends upon the improvement and advent of reactor varieties that make a greater use of the nuclear resources.

This publication is a invaluable source for reactor physicists.

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Extra info for Advances in Nuclear Science and Technology: v. 6

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METHODS OF CALCULATION A. Nuclear In order to obtain all necessary information about the core, part of which has been described above, a large number of nuclear and thermohydraulic as well as dynamic calculations had to be performed. To avoid excessive engineering costs and because of numerical difficulties certain simplifications in the calculational model had to be made; in this regard proper treatment of the actual three-dimensional very heterogeneous geometry of the core posed a problem. Therefore the nuclear calculations were divided into two classes: (a) Standard cases, treated in xy geometry, which provided the best possible values of /ceff for several "clean" axial conditions.

Further matters for consideration were the excess reactivity of the core with all control rods withdrawn, the worth of the control rods, and the reliability of the methods used to calculate the power distribution (20). In order to achieve these aims, the zero power experiments (21) were carried out in two stages. In the first stage, three quarters of the core comprised the original fuel elements in a preliminary assembled state which still allowed for the substitution of some fuel rods by burnable poison rods if this should become necessary.

To enable a comparison with theoretical values, the decay constants a were converted to a reactivity scale by the following equation: l-a/ac 1 - ßcc/ccc (1) [An explanation of this equation is given in (25)], where, p is the reactivity in dollars, ac is the fundamental mode decay constant from 30 D. BÜNEMANN ET AL. 0073) is the effective fraction of the delayed neutrons (32). The above mentioned equation setting ß/l = ß/lc = ac does not account for changes in the mean neutron lifetime /, which may occur on going from the delayed critical state to the subcritical state with changed boron concentration or changed control rod position.

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