MCNP

Known as: MCNPX, Monte Carlo N-Particle Transport 
Monte Carlo N-Particle Transport Code (MCNP) is a software package for simulating nuclear processes. It is developed by Los Alamos National… (More)
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Topic mentions per year

Topic mentions per year

1991-2018
0204019912018

Papers overview

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2013
2013
Soil moisture status in land surface models (LSMs) can be updated by assimilating cosmic-ray neutron intensity measured in air… (More)
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2013
2013
A cosmic-ray soil moisture probe is usually calibrated locally using soil samples collected within its support volume. But such… (More)
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2012
2012
This paper presents the preliminary results of PET system simulation using Monte Carlo code. We also present the implementation… (More)
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2012
2012
The IAEA, in collaboration with the Joint Research Center (Ispra, IT) and Hybrid Instruments (UK), is developing a liquid… (More)
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2011
2011
We describe a model for deploying radiation detectors on a transportation network consisting of two adversaries: a nuclear… (More)
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2010
2010
*Corresponding author: Dr. Asghar Mesbahi, Medical physics department, Medical school, Tabriz university of Medical Sciences… (More)
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2010
2010
MCNPX Monte Carlo electron transport analyses are used to characterize the electron beam facility at NEO Beam. The electron flux… (More)
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2006
2006
Introduction: In recent years, a number of studies [1,2,3] have been published using data from the Lunar Prospector Neutron… (More)
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2000
2000
MCNP is the Monte Carlo N-Particle radiation transport code whose history dates back more than half a century to the early days… (More)
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1991
1991
The authors report both the status and developments in the Monte Carlo neutron-photon (MCNP) radiation transport computer code… (More)
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