Results 81 to 90 of about 898 (171)

SKIRT: the design of a suite of input models for Monte Carlo radiative transfer simulations

, 2015
The Monte Carlo method is the most popular technique to perform radiative transfer simulations in a general 3D geometry. The algorithms behind and acceleration techniques for Monte Carlo radiative transfer are discussed extensively in the literature, and
Baes, Maarten, Camps, Peter
core   +1 more source

Efek Penambahan Plutonium pada Sel Bahan Bakar MOX terhadap Performa Reaktor GFR 250MWth [PDF]

A fast-type reactor that operates on high-speed neutrons, GFR (Gas-cooled Fast Reactor) can produce various fissile materials and fertilizers. This production capability is very beneficial for the stability of nuclear fuel in the reactor core, especially
Johan, Akmal, Kaban, Hadir, Menik Ariani, Monado, Fiber, Muhammad Aldi Kurniawan   +4 more
core   +2 more sources

Distributed OpenMP Offloading of OpenMC on Intel GPU MAX Accelerators

CoRR
Monte Carlo (MC) simulations play a pivotal role in diverse scientific and engineering domains, with applications ranging from nuclear physics to materials science. Harnessing the computational power of high-performance computing (HPC) systems, especially Graphics Processing Units (GPUs), has become essential for accelerating MC simulations. This paper
Fridman, Yehonatan, Tamir, Guy, Steinitz, Uri, Oren, Gal   +3 more
openaire   +2 more sources

Development of an Event Tracking Feature in OpenMC for Neutron Noise Analysis [PDF]

EPJ Web of Conferences
We present the development and implementation of a neutron event-tracking capability in OpenMC, an open-source, community-driven Monte Carlo radiation transport code.
Saliba Michel, Tramm John, Romano Paul, Knudsen Erik B., Pautz Andreas, Pakari Oskari   +5 more
doaj   +1 more source

Progress and Status of the Openmc Monte Carlo Code [PDF]

The present work describes the latest advances and progress in the development of the OpenMC Monte Carlo code, an open-source code originating from the Massachusetts Institute of Technology.
Forget, Benoit Robert Yves, Herman, Bryan R, Horelik, Nicholas Edward, Romano, Paul Kollath, Siegel, Andrew R., Smith, Kord S.   +5 more
core  

Benchmarking of probability tables with TRIPOLI-5® [PDF]

EPJ Web of Conferences
In this work we present the verification of the unresolved resonance range treatment implementation in the Monte Carlo code TRIPOLI-5®, which relies on probability tables.
Montecchio Cecilia, Larmier Coline, Mancusi Davide, Zoia Andrea   +3 more
doaj   +1 more source

Modeling and Analysis of Neutron Flux of a VVER 1200 Reactor Core Using Monte Carlo Code OpenMC [PDF]

Nuclear reactors and their associated facilities are complex systems that require accurate modeling and analysis to ensure safety, security, and efficient operation.
Al Hasan, K. M. Rakib, Datta, Dr. Debashis, Hossain, Altab   +2 more
core   +2 more sources

Development of BNCT Dose Calculation Function Based on cosRMC

Journal of Isotopes
To ensure the effectiveness and safety of boron neutron capture therapy (BNCT)，precise dose calculation and treatment planning are of critical importance.
Shengzhe WANG, Wei JIANG, Xunwu YANG, Peng LU, Xulei ZHANG, Lizhen LIANG   +5 more
doaj   +1 more source

Analisis Reaktivitas Thorium Molten Salt Reactor 500 Berdasarkan Skenario Penggunaan Control Rod Menggunakan OpenMC [PDF]

Neutron calculation simulation with the TMSR-500 conceptual reactor model was carried out for the development of reactivity control in the reactor. The control of reactivity is regulated by the use of a control rod for the shutdown rod and a regulating ...
Eza Pelita Zebua, Fajri, Fardela, Ramacos, Fitriyani, Dian, Handayani Irka, Feriska, Raflis, Helen   +4 more
core   +2 more sources

Extension of the OpenMC depletion module for transport-independent depletion

Proceedings of the Python in Science Conference
This paper describes new functionality in OpenMC's depletion module for depleting materials independent of a neutron transport simulation. The paper valdiates the capability against transport-coupled depletion on a simple model.
Oleksandr Yardas, Paul Romano, Madicken Muk, Kathryn Huff   +3 more
openaire   +1 more source