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Results 1-10 of 12 (Search time: 0.005 seconds).
Item hits:
Issue DateTitleAuthor(s)
Jan-1968IBM 360 version of the neutron diffusion code CRAM.McGregor, BJ; Richards, AG; Wood, RGJ
Oct-1968Some iterative methods for solving the matrix equation Ax = bDoherty, G
Mar-1966GYMEA - a nuclide depletion, space independent, multigroup neutron diffusion, data preparation code.Pollard, JP; Robinson, GS
Feb-1967Conversion of the neutron code TDC to FORTRAN IVMcGregor, BJ
Aug-1964PEAS - a resonance absorption programme.Pollard, JP
May-1966Condensed tables for x-ray fluorescence analysisBrockman, RH; Whittem, RN
Mar-1966Shutdown - a reactor shutdown optimization codeFredsall, JR
Feb-1967FORTRAN IV programmes for computation of temperature and thermoelastic stress in a homogeneous spherical fuel element due to axisymmetric heat transfer variation over the surface.Holy, ZJ
Aug-1965DEMON - a programme generator for problems involving ordinary differential equations.Bennett, NW
Oct-1966LUBRA - a code to calculate point and group cross sections, effective resonance integrals and doppler coefficients for reasonable absorbers in homogeneous reactors, using Breit-Wigner single-level resonance parameters.Kletzmayr, EK

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