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Title: A DIGITAL COMPUTER SOLUTION FOR SPACE-DEPENDENT NEUTRON KINETICS EQUATIONS

Abstract

A set of one-group space-dependent neutron kinetics equations for reactor cores with spatially variable moderator density is developed. The solution to this set of differential equations is obtained numerically using an IBM-7094 digital computer. Employing the variational technique of von Neumann, a numerical stability criterion for space-dependent neutron kinetics equations is established. The analysis is useful in the determination of the core open-loop response as well as the reactor system transient behavior. The open-loop response of a typical boiling-water reactor core for several values of step change in reactivity was determined using the analysis. These are shown to be in agreement with the results of the classical space-independent neutron kinetics equations. The open-loop characteristic of the reactor core due to a step change in density distribution is also presented. The main distinguishing feature of the present study is the ability to determine the open-loop response due to disturbances (such as a series of successive step changes in density distribution) for which the classical space-independent approach provides no solution. Characteristics of this type are necessary in the dynamic analysis of boiling-water reactors where the system density distribution varies in time and space. A simple approximate method for the solution of themore » space-dependent neutron kinetics equations is also presented. (auth)« less

Authors:
;
Publication Date:
Research Org.:
Westinghouse Electric Corp., Pittsburgh
OSTI Identifier:
4069009
NSA Number:
NSA-18-015439
Resource Type:
Journal Article
Journal Name:
Nuclear Science and Engineering (U.S.)
Additional Journal Information:
Journal Volume: Vol: 18; Other Information: Orig. Receipt Date: 31-DEC-64
Country of Publication:
Country unknown/Code not available
Language:
English
Subject:
REACTOR TECHNOLOGY; COMPUTERS; DENSITY; DIFFERENTIAL EQUATIONS; DIGITAL SYSTEMS; DISTRIBUTION; EQUATIONS; IBM 7094; MODERATORS; NEUTRONS; NUCLEATE BOILING; NUMERICALS; REACTIVITY; REACTOR CORE; REACTORS; STABILITY; TRANSIENTS; VARIATIONS; ZONES

Citation Formats

Nahavandi, A.N., and Von Hollen, R.F. A DIGITAL COMPUTER SOLUTION FOR SPACE-DEPENDENT NEUTRON KINETICS EQUATIONS. Country unknown/Code not available: N. p., 1964. Web.
Nahavandi, A.N., & Von Hollen, R.F. A DIGITAL COMPUTER SOLUTION FOR SPACE-DEPENDENT NEUTRON KINETICS EQUATIONS. Country unknown/Code not available.
Nahavandi, A.N., and Von Hollen, R.F. Sun . "A DIGITAL COMPUTER SOLUTION FOR SPACE-DEPENDENT NEUTRON KINETICS EQUATIONS". Country unknown/Code not available.
@article{osti_4069009,
title = {A DIGITAL COMPUTER SOLUTION FOR SPACE-DEPENDENT NEUTRON KINETICS EQUATIONS},
author = {Nahavandi, A.N. and Von Hollen, R.F.},
abstractNote = {A set of one-group space-dependent neutron kinetics equations for reactor cores with spatially variable moderator density is developed. The solution to this set of differential equations is obtained numerically using an IBM-7094 digital computer. Employing the variational technique of von Neumann, a numerical stability criterion for space-dependent neutron kinetics equations is established. The analysis is useful in the determination of the core open-loop response as well as the reactor system transient behavior. The open-loop response of a typical boiling-water reactor core for several values of step change in reactivity was determined using the analysis. These are shown to be in agreement with the results of the classical space-independent neutron kinetics equations. The open-loop characteristic of the reactor core due to a step change in density distribution is also presented. The main distinguishing feature of the present study is the ability to determine the open-loop response due to disturbances (such as a series of successive step changes in density distribution) for which the classical space-independent approach provides no solution. Characteristics of this type are necessary in the dynamic analysis of boiling-water reactors where the system density distribution varies in time and space. A simple approximate method for the solution of the space-dependent neutron kinetics equations is also presented. (auth)},
doi = {},
journal = {Nuclear Science and Engineering (U.S.)},
number = ,
volume = Vol: 18,
place = {Country unknown/Code not available},
year = {1964},
month = {3}
}