Results 21 to 30 of about 10,040 (154)
BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS [PDF]
EPJ Web of Conferences, 2021 Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, including, shielding, material lifetime and remote maintenance ...
Valentine A. +3 more
doaj +1 more source
Elaborate SMART MCNP Modelling Using ANSYS and Its Applications
EPJ Web of Conferences, 2017 An MCNP 3-dimensional model can be widely used to evaluate various design parameters such as a core design or shielding design. Conventionally, a simplified 3-dimensional MCNP model is applied to calculate these parameters because of the cumbersomeness ...
Song Jaehoon +3 more
doaj +1 more source
Studi Perhitungan Benchmark Kritikalitas Teras Metalik dan MOX di FCA
Jurnal Fisika Flux, 2017 The criticality experiments at FCA three cores have been done to obtain reliable original data as a benchmark test. The first two cores was mock-up of metallic fueled LMFBR’s and the other was a mock-up of a MOX fueled LMFBR.
Zuhair Zuhair +2 more
doaj +3 more sources
The Failure of Monte Carlo Radiative Transfer at Medium to High Optical Depths [PDF]
, 2018 Computer simulations of photon transport through an absorbing and/or scattering medium form an important research tool in astrophysics. Nearly all software codes performing such simulations for three-dimensional geometries employ the Monte Carlo ...
Baes, Maarten, Camps, Peter
core +2 more sources
Frontiers in Biomedical Technologies, 2020 Purpose: Gamma Knife is applied as a superseded tool for inaccessible lesions surgery delivering a single high dose to a well-defined target through 201 small beams. Monte Carlo simulations can be an appropriate supplementary tool to determine dosimetric
Atefeh Mahmoudi, Ghazale Geraily
doaj +1 more source
Reducing the radioactive doses of liquid samples taken from reprocessing plant vessels by volume reduction [PDF]
, 2007 A
Buyst, Jimmy +2 more
core +2 more sources
Simulation of the DD, TT and DT JET Neutron Streaming Experiments with TRIPOLI-4® Monte-Carlo code [PDF]
EPJ Web of ConferencesThe DD, TT and DT neutron streaming experiments (NEXP-STRE) in the fusion facility JET are here simulated with TRIPOLI-4® Monte-Carlo code. Specifically, we present the results from the simulation of the DD (2019) and the later TT and DT (2021) campaigns.
Pontier Jean-Baptiste +2 more
doaj +1 more source
Nuclear Engineering and Technology, 2019 This study systematically compared two hybrid deterministic/Monte Carlo transport codes, ADVANTG/MCNP and MAVRIC, in solving a difficult shielding problem for a real-world spent fuel storage cask.
Po-Chen Lai +2 more
doaj +1 more source
Determination of neutron spectrum parameters at IREN facility using the MCNP simulation and experimental validation [PDF]
Nuclear Technology and Radiation ProtectionThe determination of the characteristics of neutron spectrum at different irradiation positions on the outer wall of moderator chamber of the intense resonance neutron source by simulation method using MCNP code was presented.
Nhat Le Tran Minh +14 more
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Neutron shielding and activation of the MASTU device and surrounds
, 2014 A significant functional upgrade is planned for the Mega Ampere Spherical Tokamak (MAST) device, located at Culham in the UK, including the implementation of a notably greater neutral beam injection power.
Davis, Andrew +3 more
core +1 more source