Asymptotic Analysis of the Several Competitive Equations to Solve the Time-dependent Neutron Transport Equation

Asymptotic Analysis of the Several Competitive Equations to Solve the Time-dependent Neutron Transport Equation

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Publisher:

Published: 1994

Total Pages: 12

ISBN-13:

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Using conventional diffusion limit analysis, we asymptotically compare three competitive time-dependent equations (the telegrapher's equation, the time-dependent Simplified P2 (SP2) equation, and the time-dependent Simplified Evcn-Parity (SEP) equation). The time-dependent SP2 equation contains higher order asymptotic approximations of the time-dependent transport equation than the other equations in a physical regime in which the time-dependent diffusion equation is the leading order approximation. In addition, we derive the multigroup modified time-dependent SP2 equation from the multigroup time-dependent transport equation by means of an asymptotic expansion in which the multigroup time-dependent diffusion equation is the leading, order approximation. Numerical comparisons of the timedependent diffusion, the telegrapher's, the time-dependent SP2, and S solutions in 2-D X-Y geometry show that, in most cases, the SP2 solutions contain most of the transport corrections for the diffusion approximation.


Handbook of Nuclear Engineering

Handbook of Nuclear Engineering

Author: Dan Gabriel Cacuci

Publisher: Springer Science & Business Media

Published: 2010-09-14

Total Pages: 3701

ISBN-13: 0387981306

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This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.


Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations

Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations

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Publisher:

Published: 1975

Total Pages:

ISBN-13:

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In this thesis two unrelated topics of reactor physics are examined: the prompt jump approximation and alternating direction checkerboard methods. In the prompt jump approximation it is assumed that the prompt and delayed neutrons in a nuclear reactor may be described mathematically as being instantaneously in equilibrium with each other. This approximation is applied to the spatially dependent neutron diffusion theory reactor kinetics model. Alternating direction checkerboard methods are a family of finite difference alternating direction methods which may be used to solve the multigroup, multidimension, time-dependent neutron diffusion equations. The reactor mesh grid is not swept line by line or point by point as in implicit or explicit alternating direction methods; instead, the reactor mesh grid may be thought of as a checkerboard in which all the ''red squares'' and '' black squares'' are treated successively. Two members of this family of methods, the ADC and NSADC methods, are at least as good as other alternating direction methods. It has been found that the accuracy of implicit and explicit alternating direction methods can be greatly improved by the application of an exponential transformation. This transformation is incompatible with checkerboard methods. Therefore, a new formulation of the exponential transformation has been developed which is compatible with checkerboard methods and at least as good as the former transformation for other alternating direction methods. (auth).