Monte Carlo codes

While both Eulerian and Lagrangian Monte-Carlo codes have been implemented, La-grangian code offers many advantages, especially when velocity is a random variable. 

These expressions, which were calibrated from Poisson-Boltzman calculations (see below) can be easily implemented in any molecular dynamics or Monte Carlo code and also in docking programs where the speed of calculation is crucial. 

Kogler U., Winter J., ERO-TEXTOR 3D-Monte-Carlo Code for Local Impurity Modeling in the Scrape-Off-Layer of TEXTOR, Report Jill-3361, Jiilich, 1997... 

Simulating erosion and re-deposition processes in fusion devices lead to a better understanding of the processes involved. The 3-dimensional Monte-Carlo code ERO-TEXTOR [35,36] has been developed to model the plasma-wall interaction and the transport of eroded particles in the vicinity of test limiters exposed to the edge plasma of TEXTOR. Important problems concerning the lifetime of various wall materials (high Z vs. low Z) under different plasma conditions and the transport of eroded impurities into the main plasma can be treated with the ERO-TEXTOR code. Recently, the divertor geometries have been implemented to carry out simulations for JET, ASDEX and ITER [37], In addition, first attempts have been made to simulate erosion and re-deposition processes in the linear plasma device PISCES to analyze the effect of beryllium. 

An answer therefore could be a less time consuming and novel mnltistep Continnnm Monte Carlo technique to solve problems created by multiphenomena characteristics of electrochemical processes and power sources. In the case shown for a lithium ion battery cathode material three different types of Continuum Monte Carlo codes are written to solve three different electrochemical phenomena. All the codes are based on fundamental electrochemical principles, therefore invaluable physics is not lost while deriving useable data. 

Champion C, L Hoir A, PoHris ME, Fainstein PD, Rivarola RD, Chetioui A. (2005) A Monte Carlo code for the simulation of heavy-ion tracks in water. Radiat Res 163(2) 222-231. 

A radioisotope battery is one of the choice for energy source of meteorological obseiwation and development of undersea and space[l]. We have considered a strontium-90 (half-life 28.8y) heat-source model of a radioisotope battery and improved it in two aspects—radiation dose reduction and improvement of thermal conductivity—adding graded structure to the model[2]. The present study reports the dose reduction of bremsstrahlung photons from -ray of - "Sr and its daughter nuclide yttrium-90. The calculation was carried out by a continuous energy Monte Carlo code, MCNP 4A[3]. 

However, requirements for low DURs impose limits to the size and density of product loads. Theoretical relationships between these quantities when square containers of finite size are irradiated from opposite sides with 5.0 MeV X rays are shown in Fig. 5. The horizontal axes give the container size in cm, and the vertical axis gives the DUR. The four curves are for different densities ranging from 0.2 to 0.8 g/cu cm. If a DUR of 2.0 is acceptable, then the container sizes can be about 180, 100, 70 and 50 cm for densities of 0.2, 0.4, 0.6 and 0.8 g/cu cm, respectively. If a lower DUR of 1.5 is needed, then the container sizes will be limited to about 120, 60, 45 and 30 cm, respectively. These results were calculated with the GEANT3 Monte Carlo code [7, 8],... 

S.M. SELTZER, Applications of ETRAN Monte Carlo Codes, in Monte Carlo Transport of Electrons and Photons, Eds. T.M. Jenkins, W.R. Nelson and A. Rindi, Plenum Press, NY, 1988. 

Berger, M. J., and Seltzer, S. M., ETRAN Monte Carlo Code System for Electron and Photon Transport Through Extended Media, NBS-9836 and NBS-9837 (1968). 

B riesmeister, J. F. 1990. MCNP-A general Monte Carlo code for neutron and photon transport. Version 4.2. Technical Report LA-7396-M, Los Alamos National Laboratory. 

In order to derive the imaging properties of Bragg concentrators we developed a Monte Carlo code that simulates a parallel X-ray beam incident on the concentrator top. In the code the actual position of the mirror crystals, including possible misalignments of the single pieces with respect to the perfect parabolic geometry, is taken into account ((Pasqualini et al., 1992)). It... 

The Monte Carlo code MONK was originally written to replace the Monte Carlo code GEM (7-i). GEM was primarily written to help in the assessment of criticality in chemical and metallurgical plant processing fissile materials, and also in the storage and transport of these materials. MONK not only will perform these tasks but can also perform calculations of interest to the reactor physicist. In criticality assessment work, boundary tracking is quite often used, especially for problems involved in the transport of fissile materials, since this option enables interactions between several similar items to be calculated as a subsidiary calculation. Fission to fission tracking has been incorporated as an optional choice in MONK to enable the effective multiplication constant to be calculated directly from the number of neutrons in successive generations. 

A problem commonly met in criticality work is the assessment of the criticality of an array of different interacting units. In principle, a Monte Carlo code could estimate the criticality of such a system by tracking neutrons in the normal way. In large arrays the tracking time can be prohibitive. The alternative is to use a method referred to generally as the interaction parameter method 14). Let... 

P. J. Hemmings, Use of the UK Nuclear Data Library in the Monte Carlo Code MONK, AHSB(S)R184 (1970). 

Much attention is being paid to the generation of nuclear data. For the PANTHER-THERMIX system, neutron cross sections are generated by WIMS-E and SCALE-4 codes. The Monte-Carlo code MCNP is used for tiiis as well, and to check certain reactor calculations. 

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