Use of ''FASTER'' code for significantly reducing ducted reactor shield computation time
FASTER code for significantly reducing ducted reactor shield computation time for neutron number spectrum
Jordan, T. M.↗
Engineering topics
Jordan, T. M.
Publications and source records attributed to Jordan, T. M..
Synthesis of calculational methods for the design and analysis of radiation shields for nuclear rocket systems. Volume 1, synopsis of methods and results of analysis Final progress report
Monte Carlo method, kernel function, and S matrix theory applied to design and analysis radiation shields in nuclear rocket systems
Capo, M. A.↗
Synthesis of calculational methods for the design and analysis of radiation shields for nuclear rocket systems. Volume 9 - FASTER - A Fortran Analytical Solution of the Transport Equation by Random sampling Final progress report
Fortran analytic solution of transport equations by random sampling in radiation shielding design and analysis of nuclear rocket systems
Jordan, T. M.↗
Synthesis of calculational methods for the design and analysis of radiation shields for nuclear rocket systems. Volume 5 - TIC-TOC-TOE, a FORTRAN program for the temperature in the coolant tank and other calculations and for the thermal neutron originating energy Final progress report
TIC-TOC-TOE computer program for radiation shielding design and analysis in nuclear rocket systems
Jordan, T. M.↗