CALCULATION OF THERMAL NEUTRON FLUXES IN PRIMARY SHIELDS | Zendy

D. C. Anderson | Zendy; K. Shure | Zendy

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CALCULATION OF THERMAL NEUTRON FLUXES IN PRIMARY SHIELDS

Author(s) -

D. C. Anderson,

K. Shure

Publication year - 1959

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4191917

Subject(s) - shields , homogeneous , neutron , attenuation , neutron temperature , nuclear engineering , nuclear physics , kernel (algebra) , physics , computational physics , materials science , mathematics , optics , statistical physics , electromagnetic shielding , engineering , quantum mechanics , combinatorics

A method is presented for calculating thermal neutron fluxes in the primary shields of reactor systems which eliminates reliance on mock-up experimental data. A multigroup P/sub 1/ approach is ernployed with the spatial dependence of the neutron sttenuation adjusted through use of a point source attenuation kernel for a homogeneous hydrogenous medium. Comparison of calculation with experiment is presentad. (auth

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