Browsing by Author Thompson, JJ
Showing results 1 to 13 of 13
| Issue Date | Title | Author(s) |
| 1960 | The critical size of a bare spherical reactor with anisotropic diffusion. | Thompson, JJ |
| 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 |
| Nov-1956 | A note on the response of a circulating fuel reactor to random fluctuation in fuel concentration | Thompson, JJ |
| Aug-1958 | A note on thermo-elastic stress in axially symmetric anisotropic cylinders. | Thompson, JJ |
| Nov-1956 | A preliminary kinetic study of a sodium-beryllium-uranium circulating fuel reactor | Thompson, JJ |
| Feb-1966 | Response matrices in the double pN approximation of neutron transport theory | Thompson, JJ |
| Jul-1959 | Some aspects of thermal neutron diffusion in non-uniform temperature moderator | Thompson, JJ |
| Aug-1964 | Temperatures in a sphere with distributed source and variable surface heat transfer | Thompson, JJ |
| Apr-1963 | Theory and application of the double Pn method in slab geometry for isotropic neutron sources and scattering | Thompson, JJ |
| Aug-1958 | Two group theory for exploratory HTGC reactor calculation | Thompson, JJ |
| Dec-1960 | A two-group analysis of a finite fully reflected cylindrical reactor | Thompson, JJ |
| Dec-1962 | A two-group, three-region, fully reflected cylindrical reactor program for the IBM 1620 | Thompson, JJ; Godfrey, M |
