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Publications by R.W. Roussin
Sample Problems for the Novice User of the AMPX-II System. [For Generating Coupled Multigroup Neutron--Gamma Libraries, in FORTRAN IV for IBM 360/91]
VITAMIN-E: An ENDF/B-V Multigroup Cross-Section Library for LMFBR Core and Shield, LWR Shield, Dosimetry and Fusion Blanket Technology
Guide for Licensing Evaluations Using CRAC2: A Computer Program for Calculating Reactor Accident Consequences
Related publications
SIOB: A FORTRAN Code for Least-Squares Shape Fitting Several Neutron Transmission Measurements Using the Breit--Wigner Multilevel Formula. [For IBM-360/91]
Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries
Journal of ASTM International
Neutron Cross-Section Libraries in the AMPX Master Interface Format for Thermal and Fast Reactors
Numerical Solution of Helmholtz's Equation by the Capacitance Matrix Method. [In FORTRAN for IBM 360/75 Computer]
Variable Metric Method for Minimization. [In FORTRAN for IBM 704]
A Fortran Iv Crystallographic System of Programs for Generalized Superpositions.
Multigroup Neutron Transport. II. Half Range
Journal of Mathematical Physics
Nonlinear Physics
Mathematical Physics
Statistical
PIMG--A ONE-DIMENSIONAL MULTIGROUP P$sub 1$ CODE FOR THE IBM-704
Cryptographic System Enhancements for the IBM System Z9
IBM Journal of Research and Development
Computer Science
