Recent developments in the TRIPOLI-4® Monte-Carlo code for shielding and radiation protection applications

Abstract Introduction: The present study aimed to investigate the radiation protection properties of silicon-based composites doped with nano-sized Bi2O3, PbO, Sm2O3, Gd2O3, WO3, and IrO2 particles. Radiation shielding properties of Sm2O3 and IrO2 nanoparticles were investigated for the first time in the current study. Material and methods: The MCNPX (2.7.0) Monte Carlo code was utilized to calculate the linear attenuation coefficients of single and multi-nano structured composites over the X-ray energy range of 10–140 keV. Homogenous distribution of spherical nanoparticles with a diameter of 100 nm in a silicon rubber matrix was simulated. The narrow beam geometry was used to calculate the photon flux after attenuation by designed nanocomposites. Results: Based on results obtained for single nanoparticle composites, three combinations of different nano-sized fillers Sm2O3+WO3+Bi2O3, Gd2O3+WO3+Bi2O3, and Sm2O3+WO3+PbO were selected, and their shielding properties were estimated. In the energy range of 20-60 keV Sm2O3 and Gd2O3 nanoparticles, in 70-100 keV energy range WO3 and for photons energy higher than 90 keV, PbO and Bi2O3 nanoparticles showed higher attenuation. Despite its higher density, IrO2 had lower attenuation compared to other nanocomposites. The results showed that the nanocomposite containing Sm2O3, WO3, and Bi2O3 nanoparticles provided better shielding among the studied samples. Conclusions: All studied multi-nanoparticle nanocomposites provided optimum shielding properties and almost 8% higher attenuation relative to single nano-based composites over a wide range of photon energy used in diagnostic radiology. Application of these new composites is recommended in radiation protection. Further experimental studies are suggested to validate our findings.

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Recent developments of JAEA’s Monte Carlo code MVP for reactor physics applications

Annals of Nuclear Energy ◽

10.1016/j.anucene.2014.09.037 ◽

2015 ◽

Vol 82 ◽

pp. 85-89 ◽

Cited By ~ 7

Author(s):

Yasunobu Nagaya ◽

Keisuke Okumura ◽

Takamasa Mori

Keyword(s):

Monte Carlo ◽

Monte Carlo Code ◽

Reactor Physics ◽

Recent Developments

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Radiation Protection Studies for Medical Particle Accelerators using Fluka Monte Carlo Code

Radiation Protection Dosimetry ◽

10.1093/rpd/ncw302 ◽

2016 ◽

Vol 173 (1-3) ◽

pp. 185-191 ◽

Cited By ~ 1

Author(s):

Angelo Infantino ◽

Gianfranco Cicoria ◽

Giulia Lucconi ◽

Davide Pancaldi ◽

Sara Vichi ◽

...

Keyword(s):

Monte Carlo ◽

Radiation Protection ◽

Particle Accelerators ◽

Monte Carlo Code

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NUMERICAL BENCHMARK OF STRONGLY TO LOOSELY COUPLED ASSEMBLIES USING THE TRANSIENT FISSION MATRIX METHOD

EPJ Web of Conferences ◽

10.1051/epjconf/202124706038 ◽

2021 ◽

Vol 247 ◽

pp. 06038

Author(s):

K. Routsonis ◽

P. Blaise ◽

J. Tommasi

Keyword(s):

Monte Carlo ◽

Ad Hoc ◽

Experimental Program ◽

System Response ◽

Propagation Time ◽

Monte Carlo Code ◽

Water Tank ◽

Loosely Coupled ◽

Recent Developments ◽

Tightly Coupled

Advances in computational methods have given rise to the study and simulation of different aspects of reactor behavior. As such, topics associated with high computational costs become feasible candidates for further investigation and one of them is reactor space-time kinetics (STK). Until recently, STK simulation and point kinetics approximation were limited to deterministic codes, with Monte Carlo codes being too costly to start with. However, recent developments in this area have allowed the use of certain methods in stochastic codes. One such technique is based on the Transient Fission Matrix (TFM) model, a hybrid method that uses a system response obtained through Monte Carlo and stored in fission and time matrices as input for deterministic calculations. The result enables a view of the STK in terms of neutron propagation probability and propagation time across the system. The TFM method was applied to a simple coupled core configuration to generate a numerical benchmark. The Serpent 2 Monte Carlo code was used for the stochastic part of the calculation. The configuration consists of two fuel assemblies placed in a light water tank, with a water blade of varying width between them. TFM, flux and fission results were obtained for varying water blade widths, ranging between 0 cm and 20 cm. The data is then used to analyze the behavior of the system, as well as the effects of the coupling between the two assemblies. As the assemblies move further apart, the system slowly transitions from two tightly coupled assemblies that essentially form a single core, to two almost independent cores. This study enables to produce a benchmark for future calculations and predefine an innovative way of designing high dominant ratio configurations, required for tackling Monte Carlo residual problems. An actual experimental program could be led in ad hoc zero power reactor (ZPR), such as the KUCA reactor of Kyoto University.

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The Application of the Monte Carlo Code FLUKA in Radiation Protection Studies for the Large Hadron Collider

Progress in Nuclear Science and Technology ◽

10.15669/pnst.2.358 ◽

2011 ◽

Vol 2 (0) ◽

pp. 358-364 ◽

Cited By ~ 11

Author(s):

Giuseppe BATTISTONI ◽

Francesco BROGGI ◽

Markus BRUGGER ◽

Mauro CAMPANELLA ◽

Massimo CARBONI ◽

...

Keyword(s):

Monte Carlo ◽

Large Hadron Collider ◽

Radiation Protection ◽

Hadron Collider ◽

Monte Carlo Code

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Recent Developments of JAEA’s Monte Carlo Code MVP for Reactor Physics Applications

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

10.1051/snamc/201406015 ◽

2014 ◽

Cited By ~ 1

Author(s):

Yasunobu Nagaya ◽

Keisuke Okumura ◽

Takamasa Mori

Keyword(s):

Monte Carlo ◽

Monte Carlo Code ◽

Reactor Physics ◽

Recent Developments

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The Monte Carlo code MCSHAPE: Main features and recent developments

Spectrochimica Acta Part B Atomic Spectroscopy ◽

10.1016/j.sab.2015.02.005 ◽

2015 ◽

Vol 108 ◽

pp. 53-60 ◽

Cited By ~ 2

Author(s):

Viviana Scot ◽

Jorge E. Fernandez

Keyword(s):

Monte Carlo ◽

Monte Carlo Code ◽

Recent Developments

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Monte Carlo simulation of photons backscattering from various thicknesses of lead layered over concrete for energies 0.25–20 MeV using FLUKA code

Scientific Reports ◽

10.1038/s41598-021-96026-y ◽

2021 ◽

Vol 11 (1) ◽

Author(s):

Ihsan A. M. Al-Affan ◽

Mohammad A. Z. Qutub ◽

Richard P. Hugtenburg

Keyword(s):

Monte Carlo ◽

Reflection Coefficient ◽

Radiation Protection ◽

Published Data ◽

Reflection Coefficients ◽

Monte Carlo Code ◽

Concrete Wall ◽

Ordinary Concrete ◽

Room Design ◽

Space Requirements

AbstractThere is an increased interest in determining the photon reflection coefficient for layered systems consisting of lead (Pb) and concrete. The generation of accurate reflection coefficient data has implications for many fields, especially radiation protection, industry, and radiotherapy room design. Therefore, this study aims to calculate the reflection coefficients of photons for various lead thicknesses covering the concrete. This new data for lead, layered over concrete, supports various applications, such as an improved design of the mazes used for radiotherapy rooms, which helps to reduce cost and space requirements. The FLUKA Monte Carlo code was used to calculate photon reflection coefficients for a concrete wall with different energies. The reflection coefficient was also calculated for a concrete wall covered by varying thicknesses of lead to study the effect of lining this metal on the concrete wall. The concrete's reflection coefficient data were compared to internationally published data and showed that Monte Carlo calculations differed significantly from some of the extrapolated data. The absorbed dose of backscattered photons for various thicknesses of lead covering the ordinary concrete has been tabulated as a function of the reflection angle. Also, the reflection coefficient as a function of the Pb thicknesses covering the ordinary concrete has been figured to study the dose reduction factor. The generation of accurate data for reflection coefficients is vital for many fields, especially for radiation protection and radiotherapy room design. The new data have been presented for lead layered over concrete in various applications, such as an improvement in the design of the mazes used for radiotherapy rooms, thereby reducing the cost and space requirements. In addition, the Monte Carlo method enables calculating the energy distribution of reflected photons, and these were shown for a range of angles.

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