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Browsing by Author Thompson, JJ

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Issue DateTitleAuthor(s)
Nov-1961Fuel element transient temperature studies.Thompson, JJ
Jul-1961Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for monte carlo applications.Thompson, JJ
Nov-1956Note on the response of a circulating fuel reactor to random fluctuation in fuel concentration.Thompson, JJ
Aug-1958Note on thermo-elastic stress in axially symmetric anisotropic cylinders.Thompson, JJ
Nov-1956Preliminary kinetic study of a sodium-beryllium-uranium circulating fuel reactor.Thompson, JJ
Feb-1966Response matrices in the double pN approximation of neutron transport theory.Thompson, JJ
Jul-1959Some aspects of thermal neutron diffusion in non-uniform temperature moderator.Thompson, JJ
Aug-1964Temperatures in a sphere with distributed source and variable surface heat transfer.Thompson, JJ
Apr-1963Theory and application of the double Pn method in slab geometry for isotropic neutron sources and scattering.Thompson, JJ
Aug-1958Two group theory for exploratory HTGC reactor calculation.Thompson, JJ
Dec-1962Two group, three-region, fully reflected cylindrical reactor program for the IBM 1620.Thompson, JJ; Godfrey, M
Dec-1960Two-group analysis of a finite fully reflected cylindrical reactor.Thompson, JJ
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