Results 31 to 40 of about 2,294 (180)
MCNP calculations of neutron emission anisotropy caused by the GIT-12 hardware
Nukleonika, 2015 The MCNP6 and MCNPX calculations for the GIT-12 device in Tomsk were performed to determine the influence of the gas-puff hardware on the neutron emission anisotropy and the neutron scattering rate.
Šíla Ondřej +4 more
doaj +1 more source
Nuclear waste characterization using Bayesian methods [PDF]
EPJ Web of ConferencesThe relance of the nuclear industrial sector in France is an ambitious plan expected to meet the energy needs of the general public in the 21st century. Along with the construction of new nuclear power plants, advancements are taking place in the fields ...
Chalil Achment +5 more
doaj +1 more source
, 1997 The Monte Carlo code MCNP-DSP was developed from the Los Alamos MCNP4a code to calculate the time and frequency response statistics obtained from subcritical measurements. The code can be used to simulate a variety of subcritical measurements including source-driven noise analysis, Rossi-{alpha}, pulsed source, passive frequency analysis, multiplicity,
openaire +3 more sources
MCNP: Neutron benchmark problems [PDF]
, 1991 The recent widespread and increased use of radiation transport codes has produced greater user and institutional demand for assurances that such codes give correct results. Responding to these requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on criticality, pulsed sphere, and shielding neutron ...
Whalen, D. J. +3 more
openaire +2 more sources
Study on efficiency calibrating method of well-type γ ray spectrometer for soil samples
He jishu, 2021 BackgroundPutting samples into the well-type γ ray spectrometer can greatly improve the activity measurement efficiency, therefore it can reduce the measurement time and the mass of samples.PurposeThis study aims to accurately obtain detection ...
LAI Yongfang +4 more
doaj +1 more source
Numerical Solution of Governing Thermal-Hydraulic Equations in the Core of PBMR Using the Porous Media Model [PDF]
مجله علوم و فنون هستهای, 2014 Numerical solution of governing thermal-hydraulic equations in the core of a pebble bed modular reactor (PBMR) is investigated using the porous media approach.
Mohammad Hossein Estaki +3 more
doaj
Potential MCNP Enhancements for NCT [PDF]
, 1993 MCNP,1 a Los Alamos National Laboratory Monte Carlo radiation transport code, is currently widely used in the medical community for a variety of purposes including treatment planning, diagnostics, beam design, tomographic studies, and radiation protection.
Estes, G. P., Taylor, W. M.
openaire +1 more source
Study of Self-Absorption in Gamma-Ray Spectroscopy of Environmental Samples [PDF]
مجله علوم و فنون هستهای, 2014 HPGe detector has been simulated by using MCNP code, and the detector response has been determined. Monte Carlo simulations have been performed for different elemental composition and density as environmental Marinelli samples (z =10-90, ρ = 0.8-2 g/cm3).
Mahboobeh Lotfi +2 more
doaj
Calculation of Dose Distribution in Neutron Brachytherapy Using 252-Cf Source Through the Monte Carlo Simulation and Comparison with Experimental Data [PDF]
مجله علوم و فنون هستهای, 2018 Detailed recognition of dose distribution around the brachytherapy sources in order to create appropriate plans for treatment of cancer is very important.
Gh Izadi Vasafi +2 more
doaj +1 more source
Dose modeling of superficial brachytherapy applicator geometries using multiple radioisotopes
Medical Physics, Volume 53, Issue 9, September 2026.Abstract Background Superficial brachytherapy enables localized dose delivery for superficial cutaneous lesions, but conventional applicators may be limited in treating extended, irregular, or curved surfaces. Geometric constraints, gaps or overlaps between adjacent applicators, and placement‐related uncertainties can reduce dose uniformity ...
Jin Jegal +5 more
wiley +1 more source