MCMG: A 3-D Multigroup P3 Monte Carlo Code and Its Benchmarks
نویسندگان
چکیده
منابع مشابه
Application of IRDF2002 dosimetry data to shielding benchmarks using the Monte Carlo code MCBEND
The IRDF2002 dosimetry cross-section data are processed into very fine energy groups and added to the detector response library for the Monte Carlo code MCBEND. The IRDF2002 covariances are processed into broad groups to form a MCBEND detector covariance library. A number of benchmark experiments are analysed using MCBEND with both IRDF2002 and IRDF90 data and the results compared. Uncertaintie...
متن کاملRabbit internal dosimetry for iodine-131 using GATE Monte Carlo simulation code: a preclinical trial
Introduction: One of the main concerns in administration of radiotracers, especially in therapeutic arm, is the amount of delivered dose to the different organs. Individual variations of anatomy, physiology and underlying pathology in the patients lead to alteration of administered activity. In the current study we preclinically applied internal dosimetry using an animal mod...
متن کاملUpgrade of the Monte Carlo code FIDO
During rf heating on minority ions and current drive the velocity distribution is determined by the balance between the wave-particle interaction and the relaxation through Coulomb collision. This is simulated by the Monte Carlo code fido [1–3], which solves the Fokker-Planck equation in the low collisionality banana-transport regime, including finite orbit width and rf induced transport. The f...
متن کامل2 - D Compaction A Monte Carlo Method
In this paper we study the two-dimensional compaction of integrated circuit layouts. A curvilinear representation for circuit elements, specifically chosen to make the compaction efficient, is developed. A Monte Carlo algorithm with heuristic termination criteria was applied to a variety of designs. These experiments give running times for compaction that are consistent with a conjectured avera...
متن کاملA Monte Carlo Burnup Code Linking Mcnp and Rebus*
The REBUS-3 burnup code, used in the ANL RERTR Program, is a very general code that uses diffusion theory (DIF3D) to obtain the fluxes required for reactor burnup analyses. Diffusion theory works well for most reactors. However, to include the effects of exact geometry and strong absorbers that are difficult to model using diffusion theory, a Monte Carlo method is required. MCNP, “a general-pur...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: Journal of Nuclear Science and Technology
سال: 2000
ISSN: 0022-3131,1881-1248
DOI: 10.1080/18811248.2000.9714937