CAVEAT - A revised version of the general purpose Monte Carlo program, COHORT. Volume 1 - Theory and techniques
Revised version of general purpose Monte Carlo computer code for radiation transport calculations - theory and techniques
Byrn, N. R.↗
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CAVEAT - A revised version of the general purpose Monte Carlo program, COHORT Volume 2 - Users' manual
Revised version of general purpose Monte Carlo computer code for radiation transport calculations - users manual
Byrn, N. R.↗
Probability distributions and error estimates for Monte Carlo solutions of radiation problems
Probability distributions and error estimates for Monte Carlo solutions of radiation heat transfer problems, considering wavelength and direction of emitted photon bundles
Haji-Sheikh, A.↗
Monte Carlo solutions of mass, momentum and energy transfer for free molecule and near-free molecule flow through circular tubes
Monte Carlo analysis of free and near free molecular flow through circular tubes for mass, momentum and energy transfer
Fan, C.↗
A Monte Carlo technique for determining sphere drag in near free molecular flow
First collision Monte Carlo method for calculating aerodynamic drag on hard sphere and Maxwell molecular models in near-free molecular flow
Robertson, S. J.↗
Monte Carlo modeling of the Martian atmosphere from Viking mission design point of view
Martian atmosphere modeling for obtaining Viking lander spacecraft design margins by Monte Carlo method
Mukhopadhyay, A. K.↗
A regression method for the Monte Carlo evaluation of multidimensional integrals
Multidimensional integral Monte Carlo evaluation applying regression analysis to linear unbiased estimators
Cranley, R.↗
Shield weight optimization using Monte Carlo transport calculations
Monte Carlo calculations of neutron and gamma ray transport and minimum shield weight for mobile nuclear reactors
Jordan, T. M.↗
Variance reduction by importance sampling and the method of splitting in Monte Carlo calculations
Variance reduction by importance sampling and method of splitting in Monte Carlo calculations
Rosenbaum, B. M.↗
COHORT 2 - A Monte Carlo general purpose shielding computer code
Monte Carlo general purpose shielding computer program in FORTRAN 4 for IBM 7094
Clemons, L., Jr.↗
A preliminary Monte-Carlo analysis of the reflection of an imploding hemispherical shock wave similar to that generated in the UTIAS implosion driven hypervelocity launcher or shock tube
Cold wall and multibody collision effects on reflection of imploding shock waves using Monte Carlo method and molecular dynamics
Macpherson, A. K.↗
Monte Carlo direct simulation technique user's manual
User manual for Monte Carlo direct simulation technique
Vogenitz, F. W.↗
Monte Carlo evaluation of the temperature dependence of molecular transport integrals
Monte Carlo evaluation of molecular transport property integrals temperature dependence
Rehm, R. G.↗
Monte Carlo dynamic analysis for lunar module landing loads
Apollo lunar module structural integrity for lunar landing verified by Monte Carlo dynamic analysis
Merchant, D. H.↗
Shield weight optimization using Monte Carlo transport calculations
Reactor shield weight optimization using FASTER-III Monte Carlo computer program for neutron and gamma ray transport
Jordan, T. M.↗
The modulation of galactic protons by the solar wind - A Monte Carlo approach
Solar wind modulation effects on galactic protons and cosmic rays, using radial magnetic field mathematical model and Monte Carlo method
Giuli, R. T.↗
Monte Carlo simulation of the Apollo Command Module land landing
Apollo command module land landing capability in case of abort after liftoff, describing Monte Carlo simulation procedure
Chenoweth, H. B.↗
FASTER 3: A generalized-geometry Monte Carlo computer program for the transport of neutrons and gamma rays. Volume 1: Summary report
The theory used in FASTER-III, a Monte Carlo computer program for the transport of neutrons and gamma rays in complex geometries, is outlined. The program includes the treatment of geometric regions bounded by quadratic and quadric surfaces with multiple radiation sources which have specified space, angle, and energy dependence. The program calculates, using importance sampling, the resulting number and energy fluxes at specified point, surface, and volume detectors. It can also calculate minimum weight shield configuration meeting a specified dose rate constraint. Results are presented for sample problems involving primary neutron, and primary and secondary photon, transport in a spherical reactor shield configuration.
Jordan, T. M.↗