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Kinetic methods in Monte Carlo code RMC and its implementation to C5G7-TD benchmark
Annals of Nuclear Energy
◽
10.1016/j.anucene.2020.107864
◽
2021
◽
Vol 151
◽
pp. 107864
Author(s):
Xiaoyu Guo
◽
Xiaotong Shang
◽
Jing Song
◽
Guanlin Shi
◽
Shanfang Huang
◽
...
Keyword(s):
Monte Carlo
◽
Monte Carlo Code
◽
Kinetic Methods
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SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
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10.1051/snamc/201401102
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A technique for estimating neutron fluxes in a large number of in-core detectors by the Monte Carlo code PRIZMA for a full-scale model of a water-moderated reactor core
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
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10.1051/snamc/201405313
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TRIPOLI-4®, CEA, EDF and AREVA Reference Monte Carlo Code
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
◽
10.1051/snamc/201406023
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2014
◽
Author(s):
◽
E. Brun
◽
F. Damian
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C.M. Diop
◽
E. Dumonteil
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...
Keyword(s):
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Usage of burnt fuel isotopic compositions from engineering codes in Monte-Carlo code calculations
Kerntechnik
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10.3139/124.110515
◽
2015
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Vol 80
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pp. 394-401
◽
Cited By ~ 1
Author(s):
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Keyword(s):
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FRED: a fast Monte Carlo code on GPU for quality control in Particle Therapy
Journal of Physics Conference Series
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10.1088/1742-6596/1548/1/012020
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2020
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Vol 1548
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pp. 012020
Author(s):
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M Fischetti
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E Gioscio
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M Marafini
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Improvement of sensitivity and uncertainty analysis capabilities of generalized response in Monte Carlo code RMC
Annals of Nuclear Energy
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10.1016/j.anucene.2020.108099
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Yuchuan Guo
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Zhiyuan Feng
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Kan Wang
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Keyword(s):
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Uncertainty Analysis
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Monte Carlo Code
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Sensitivity And Uncertainty Analysis
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Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC
Nuclear Science and Engineering
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Steady State Analysis
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Fuel Elements
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Simulating the radiation shielding properties of TeO2–Na2O–TiO glass system using PHITS Monte Carlo code
Computational Materials Science
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10.1016/j.commatsci.2021.110566
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Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
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New Dosimetric Interpretation of the DV50 Vessel-Steel Experiment Irradiated in the OSIRIS MTR Reactor Using the Monte-Carlo Code TRIPOLI-4®
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