FRED: a fast Monte Carlo code on GPU for quality control in Particle Therapy

Journal of Physics Conference Series ◽

10.1088/1742-6596/1548/1/012020 ◽

2020 ◽

Vol 1548 ◽

pp. 012020

Author(s):

M De Simoni ◽

M Fischetti ◽

E Gioscio ◽

M Marafini ◽

R Mirabelli ◽

...

Keyword(s):

Quality Control ◽

Monte Carlo ◽

Particle Therapy ◽

Monte Carlo Code

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X-ray simulation with the Monte Carlo code PENELOPE. Application to Quality Control

2012 Annual International Conference of the IEEE Engineering in Medicine and Biology Society ◽

10.1109/embc.2012.6347307 ◽

2012 ◽

Cited By ~ 1

Author(s):

F. Pozuelo ◽

S. Gallardo ◽

A. Querol ◽

G. Verdu ◽

J. Rodenas

Keyword(s):

Quality Control ◽

Monte Carlo ◽

Monte Carlo Code ◽

X Ray

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SU-E-T-590: Optimizing Magnetic Field Strengths with Matlab for An Ion-Optic System in Particle Therapy Consisting of Two Quadrupole Magnets for Subsequent Simulations with the Monte-Carlo Code FLUKA

Medical Physics ◽

10.1118/1.4924953 ◽

2015 ◽

Vol 42 (6Part21) ◽

pp. 3471-3472

Author(s):

K Baumann ◽

U Weber ◽

Y Simeonov ◽

K Zink

Keyword(s):

Magnetic Field ◽

Monte Carlo ◽

Particle Therapy ◽

Monte Carlo Code ◽

Optic System ◽

Field Strengths

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Optimization of geometry, material and economic parameters of a two-zone subcritical reactor for transmutation of nuclear waste with SERPENT Monte Carlo code

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo ◽

10.1051/snamc/201401102 ◽

2014 ◽

Author(s):

Volodymyr Gulik ◽

Alan Henry Tkaczyk

Keyword(s):

Monte Carlo ◽

Nuclear Waste ◽

Monte Carlo Code ◽

Economic Parameters ◽

Optimization Of Geometry ◽

Subcritical Reactor

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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 ◽

10.1051/snamc/201405313 ◽

2014 ◽

Cited By ~ 1

Author(s):

Y.Z. Kandiev ◽

E.A. Kashaeva ◽

G.N. Malyshkin ◽

K.E. Khatuntsev

Keyword(s):

Monte Carlo ◽

Reactor Core ◽

Full Scale ◽

Scale Model ◽

Monte Carlo Code

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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 ◽

2014 ◽

Author(s):

◽

E. Brun ◽

F. Damian ◽

C.M. Diop ◽

E. Dumonteil ◽

...

Keyword(s):

Monte Carlo ◽

Monte Carlo Code

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Usage of burnt fuel isotopic compositions from engineering codes in Monte-Carlo code calculations

Kerntechnik ◽

10.3139/124.110515 ◽

2015 ◽

Vol 80 (4) ◽

pp. 394-401 ◽

Cited By ~ 1

Author(s):

S. S. Aleshin ◽

S. S. Gorodkov ◽

A. I. Shcherenko

Keyword(s):

Monte Carlo ◽

Monte Carlo Code ◽

Isotopic Compositions

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Improvement of sensitivity and uncertainty analysis capabilities of generalized response in Monte Carlo code RMC

Annals of Nuclear Energy ◽

10.1016/j.anucene.2020.108099 ◽

2021 ◽

Vol 154 ◽

pp. 108099

Author(s):

Guanlin Shi ◽

Yuchuan Guo ◽

Conglong Jia ◽

Zhiyuan Feng ◽

Kan Wang ◽

...

Keyword(s):

Monte Carlo ◽

Uncertainty Analysis ◽

Monte Carlo Code ◽

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 ◽

10.1080/00295639.2020.1839342 ◽

2021 ◽

pp. 1-14

Author(s):

HyeonTae Kim ◽

Yonghee Kim

Keyword(s):

Monte Carlo ◽

Steady State ◽

Unstructured Mesh ◽

Three Dimensional ◽

Monte Carlo Code ◽

Steady State Analysis ◽

Fuel Elements ◽

State Analysis

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Simulating the radiation shielding properties of TeO2–Na2O–TiO glass system using PHITS Monte Carlo code

Computational Materials Science ◽

10.1016/j.commatsci.2021.110566 ◽

2021 ◽

Vol 196 ◽

pp. 110566

Author(s):

Jamila S. Alzahrani ◽

Miysoon A. Alothman ◽

Canel Eke ◽

Hanan Al-Ghamdi ◽

Dalal Abdulldh Aloraini ◽

...

Keyword(s):

Monte Carlo ◽

Radiation Shielding ◽

Glass System ◽

Monte Carlo Code ◽

Shielding Properties

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Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis

Nuclear Engineering and Technology ◽

10.1016/j.net.2021.03.005 ◽

2021 ◽

Author(s):

Tung Dong Cao Nguyen ◽

Hyunsuk Lee ◽

Deokjung Lee

Keyword(s):

Monte Carlo ◽

Cross Section ◽

Fast Reactor ◽

Monte Carlo Code

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