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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…
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Related topics
Related topics
8 relations
Computational physics
Constructive solid geometry
FLUKA Particle Transport Code
Geant4
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Papers overview
Semantic Scholar uses AI to extract papers important to this topic.
2014
2014
Bulk shielding for laser research centre ELI Beamlines
V. Olšovcová
,
R. Haley
,
Lewis MacFarlene
,
B. Rus
,
M. Griffiths
2014
Corpus ID: 73625150
The civil structure for the laser research centre ELI Beamlines has been designed to provide adequate radiation protection for…
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2011
2011
Calculation of Neutron Contamination from Medical Linear Accelerator in Treatment Room
S. Zabihinpoor
2011
Corpus ID: 14720358
The electron linear accelerators (linac) which are used in radiography and radiotherapy applications with photon energy over 8…
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2011
2011
Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel
A. Lafleur
2011
Corpus ID: 136895756
Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel. (August…
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2010
2010
Radiation Shielding of Fusion Systems
A. Davis
2010
Corpus ID: 108120465
This thesis discusses the development, benchmarking and applications of activation dose analysis methods for fusion devices. The…
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2008
2008
NONDESTRUCTIVE MEASUREMENTS OF FISSILE MATERIAL USING SELF-INDICATION NEUTRON RESONANCE ABSORPTION DENSITOMETRY (SINRAD)
A. Lafleur
,
W. Charlton
,
H. Menlove
,
M. Swinhoe
2008
Corpus ID: 9176152
The use of self-indication neutron resonance absorption densitometry (SINRAD) to nondestructively measure the concentration of…
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2008
2008
A broad spectrum neutron spectrometer utilizing a high energy Bonner sphere extension
E. Burgett
2008
Corpus ID: 125658390
2006
2006
Incorporation of a predictor-corrector methodology and 1-group reaction rate reporting scheme for the MCNPX depletion capability
M. Fensin
,
J. Hendricks
,
H. Trellue
,
Samim Anghie
2006
Corpus ID: 124241338
2002
2002
Validation suite for MCNP
R. Mosteller
2002
Corpus ID: 59624280
Two validation suites, one for criticality and another for radiation shielding, have been defined and tested for the MCNP Monte…
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2002
2002
Measurement of Total Cross-Sections of Natural In and Cu at the Pohang Neutron Facility
VadimSkoy
,
YoungSeokLee
,
+7 authors
DongchulSon
2002
Corpus ID: 55160583
The Pohang Neutron Facility consists of an electron linear accelerator, a water-cooled Ta target, and an 11-m time-of-flight path…
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2002
2002
Radiation transport in voxel geometries: an integrated approach based on an extended version of MCNPX
K. Burn
,
C. Daffara
,
G. Gualdrini
,
M. Pierantoni
2002
Corpus ID: 182735700