Results 41 to 50 of about 1,181 (179)
Calculation of the performance of 3He alternative detectors with MCNPX [PDF]
This paper describes the techniques that are available to calculate the performance of 3He alternative detectors using MCNPX. Calculations of the performance of safeguards detectors that use 3He have been successfully carried out for many years. In the case of coincidence or multiplicity counting, specific tallies have been implemented to calculate the
Swinhoe, Martyn T. Los Alamos National Laboratory +1 more
openaire +1 more source
Gamma Shielding Experiment Simulation utilizing MCNPX Code
Experimental investigation requires materials, radiation sources, and test arrangements with a high monetary financial plan. Furthermore, radiation exposure involves people during the experiment.
Shafiqul Islam Faisal +1 more
doaj +1 more source
مقاله پژوهشی: تعیین بیشترین میزان فعالیت مجاز چشمۀ میلهای کبالتـ60 برای وجههای کاربردی مختلف در داخل اتاقک سربی [PDF]
محصورسازی چشمههای تابش یکی از مهمترین روشهای کنترل خطرات بهداشت محیط برای جلوگیری از آسیبرسانی به انسآنهاست. معمولاً از اتاقک سربی با دیوارهایی از آجر سربی برای محصورسازی چشمههای دارای خطر پرتوزایی متوسط و کم استفاده میشود.
رضا باقری +1 more
doaj +1 more source
We report some fundamental gamma-ray shielding properties and individual transmission factors (TFs) of five distinct glass samples with a nominal composition of xSb2O3·(40 − x)PbO·60B2O3·0.5CuO and (where; 0 ≤ x ≤ 40 mol%). Phy-X/PSD and MCNPX (version 2.
ALMisned Ghada +6 more
doaj +1 more source
MCNPX Improvements for Threat Reduction Applications
Enhancements contained in the current MCNPX 2.6.0 Radiation Safety Information Computational Center (RSICC) release will be presented, including stopped‐muon physics, delayed neutron and photon generation, and automatic generation of source photons. Preliminary benchmarking comparisons with data taken with a muon beam at the Paul Scherrer Institute ...
Laurie S. Waters +16 more
openaire +2 more sources
MCNPX Model/Table Comparison [PDF]
MCNPX is a Monte Carlo N-Particle radiation transport code extending the capabilities of MCNP4C. As with MCNP, MCNPX uses nuclear data tables to transport neutrons, photons, and electrons. Unlike MCNP, MCNPX also uses (1) nuclear data tables to transport protons; (2) physics models to transport 30 additional particle types (deuterons, tritons, alphas ...
openaire +2 more sources
Mechanical properties, elastic moduli, transmission factors (TFs), and gamma-ray shielding performance of quaternary glass systems with chemical composition (0.25−x)Bi2O3–xB2O3−0.75(50%P2O5−50%V2O5), where x = 0.05 (S1), 0.10 (S2), 0.15 (S3), and 0.20 ...
Tekin Huseyin Ozan +8 more
doaj +1 more source
Verification of calculations of the depth-dose distributions in water, using GEANT4 (version of 4.9.3) and MCNPX (version of 2.7.0) Monte Carlo codes, was performed for the scatterer-phantom system used in the dosimetry measurements in the proton therapy
Grządziel Małgorzata +4 more
doaj +1 more source
MCNPX benchmark for cosmic ray interactions with the Moon [PDF]
The MCNPX radiation transport code is used to simulate cosmic ray interactions within the Moon. Accurate source, geometric, and physics models are developed to successfully benchmark neutron density results with Apollo 17 measurements. The peak of the MCNPX lunar neutron density profile is shown to be within a few percent of the measured value, using a
G. W. McKinney +5 more
openaire +1 more source
Abstract Surface processes on the asteroid Ryugu have been investigated using cosmic‐ray‐produced radionuclides, 10Be, 26Al, and 36Cl, and stable noble gases, on eight samples returned by the Hayabusa2 spacecraft. The 10Be and 26Al along with 21Ne measurements indicate that the two Chamber A samples A0105 collected during the first touchdown (TD) were ...
Kunihiko Nishiizumi +30 more
wiley +1 more source

