Monte Carlo N-Particle Transport Code
- Monte Carlo N-Particle Transport Code
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Monte Carlo N-Particle Transport Code (MCNP) is a software package for simulating nuclear processes. It is developed by Los Alamos National Laboratory and is distributed within the United States by the Radiation Safety Information Computational Center in Oak Ridge, TN and internationally by the Nuclear Energy Agency in Paris, France. It is used primarily for the simulation of nuclear processes, such as fission, but has the capability to simulate particle interactions involving neutrons, photons, and electrons. "Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, detector design and analysis, nuclear oil well logging, accelerator target design, fission and fusion reactor design, decontamination and decommissioning."
MCNPX (Monte Carlo N-Particle eXtended) was also developed at Los Alamos National Laboratory, and is capable of simulating particle interactions of 34 different types of particles (nucleons and ions) and 2000+ heavy ions at nearly all energies,[1] including those simulated by MCNP.
Both codes can be used to judge whether or not nuclear systems are critical and to determine doses from sources, among other things.
Notes
- ^ https://mcnpx.lanl.gov/opendocs/misc/FeaturesList.pdf
See also
External links
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2010.
Look at other dictionaries:
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MCNP — Monte Carlo N Particle transport Le code de simulation Monte Carlo N Particle [MCNP] est un code utilisant la méthode de Monte Carlo pour simuler des processus nucléaires. Développé par le Laboratoire national de Los Alamos qui reste détenteur du … Wikipédia en Français
MCNP — Monte Carlo N Particle Transport Code Тип Вычислительная физика Математическое моделирование Разработчик Лос Аламосская национальная лаборатория Операционная система кроссплатформенное ПО Последняя версия MCNP 5.1.40 Сайт … Википедия
