Analysis of Neutron Flux in the Shielding of the Sodium Reactor Experiment
Author: F. L. Fillmore
Publisher:
Published: 1958
Total Pages: 34
ISBN-13:
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Author: F. L. Fillmore
Publisher:
Published: 1958
Total Pages: 34
ISBN-13:
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Publisher:
Published: 1958
Total Pages:
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DOWNLOAD EBOOKThe development of a matrix method of solving multigroup diffusion equations in nonmultiplying regions is described. The method is applied to a three-region shielding problem, and comparison is made with experimental results. Equations obtained by this technique can be solved with a desk calculator. (auth).
Author: F. D. Anderson
Publisher:
Published: 1959
Total Pages: 60
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DOWNLOAD EBOOKAuthor: A. R. Vernon
Publisher:
Published: 1957
Total Pages: 30
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Published: 1959
Total Pages:
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DOWNLOAD EBOOKThe experimental program performed in the SRE auxiliary and main primary galleries was part of a program to determine the adequacy of the shielding configuration for the SRE. The work discussed in this report is concerned with analysis of neutron streaming at coolant pipe penetrations of the reactor vessel, analysis of the shielding required, testing and evaluation of recommended shielding, and measurement and correlation of neutron streaming in labyrinths with theory. The activation analysis method using zinc sheets which was developed for the program of determining thermal neutron streaming in the SRE primary galleries was proven to be versatile, accurate, and reliable. A modified form of the theoretical method of Price, Horton, and Spinney, used to determine neutron scattring through labyrinths, was found to agree favorably with the experimental results obtained from the SRE primary galleries. The theoretical attenuation method used no determine the neutron shield configuration installed in the auxiliary primary gallery was found to give an overestimate of the actual attenuation properties of this shield. The neutron shield configuration installed in the auxiliary primary gallery proved to be adequate in reducing the thermal neutron streaming flux to an acceptable level. It is concluded that both SRE primary galleries are now adequately shielded to prevent excessive neutron- induced activation of the components and equipment located therein. (auth).
Author: J. B. Williams
Publisher:
Published: 1959
Total Pages: 56
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DOWNLOAD EBOOKAuthor: D. C. Anderson
Publisher:
Published: 1959
Total Pages: 46
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DOWNLOAD EBOOKAuthor: Robert W. Roussin
Publisher:
Published: 1977
Total Pages: 924
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Published: 1959
Total Pages:
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DOWNLOAD EBOOKThe thermal neutron flux distributions for the Sodium Reactor Experiment and the Hallam Power Reacter radial shields are calculated by three different methods. The method giving the highest fluxes is used to calculate conservative values of the heat generation rates in these shields. (T.F.H.).