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Issue Date	Title	Author(s)
Nov-1961	Fuel element transient temperature studies.	Thompson, JJ
Jul-1961	Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for Monte Carlo applications.	Thompson, JJ
Dec-1962	A two-group, three-region, fully reflected cylindrical reactor program for the IBM 1620	Thompson, JJ; Godfrey, M
Apr-1963	Theory and application of the double Pn method in slab geometry for isotropic neutron sources and scattering	Thompson, JJ
Dec-1960	A two-group analysis of a finite fully reflected cylindrical reactor	Thompson, JJ
1960	The critical size of a bare spherical reactor with anisotropic diffusion.	Thompson, JJ
Aug-1964	Temperatures in a sphere with distributed source and variable surface heat transfer	Thompson, JJ
Feb-1966	Response matrices in the double pN approximation of neutron transport theory	Thompson, JJ