Results 81 to 90 of about 16,330 (259)
Neutron Activation and Layout Optimization Experiments by MCNP Code for the Main Elements of Cement [PDF]
Iran is the fourth largest cement producing country in the world, and one of the pioneers in this industry. For this reason, study and further research in the fields related to the cement industry are of great importance.
S.A. Safari +2 more
doaj
An Algorithm of Converting UG Model to MCNP Geometry Model
MCNP input file has the characteristics of complicated form and is error-prone in describing geometry model. An algorithm of converting UG model to MCNP geometry model was researched and implemented through UG OPEN API and C++ programming language.
Jian Sheng Zhang, Xi Zhan
core +1 more source
MCNP output data analysis with ROOT (MODAR)
MCNP Output Data Analysis with ROOT (MODAR) is a tool based on CERN's ROOT software. MODAR has been designed to handle time-energy data issued by MCNP simulations of neutron inspection devices using the associated particle technique.
C. Carasco (8093471)
core +2 more sources
X‐ray and γ‐ray Sensing from Aqueous‐Based Lead Sulfide Telluride Nanocomposites
PbSxTey nanoparticles integrate into flexible, size‐scalable aramid polymeric scaffolds, forming percolation paths capable of efficiently transporting the electrons and holes created by penetrating photonic interactions. The resulting nanosemiconductor‐nanofiber composite forms the basis for room‐temperature spectroscopic sensors of X‐rays and γ‐rays ...
Vinh‐Dien Le +6 more
wiley +1 more source
APPLICATION OF MCNP FOR PREDICTING POWER EXCURSION DURING LOCA IN ATUCHA-2 PHWR
This thesis consists in the developing and application of a methodology based on MCNP code to predict power and reactivity excursions depending on different representation of physical variables.
PECCHIA, MARCO
core
Criticality calculations with MCNP{trademark}: A primer
With the closure of many experimental facilities, the nuclear criticality safety analyst increasingly is required to rely on computer calculations to identify safe limits for the handling and storage of fissile materials.
Briesmeister, J. F. +3 more
core +1 more source
Despite extensive efforts in studying radioactive aerosols, including the transmission of radionuclides in different chemical matrices throughout the body, the internal organ-specific radiation dose due to inhaled radioactive aerosols has largely relied ...
Khaled Talaat +3 more
semanticscholar +1 more source
Introducing a Method to Derive a Multiple Virtual Point Source Model of Linac for Photon Beam Dose Calculation Using Monte Carlo Method [PDF]
In this study a new simple but a very effective method is introduced for the beam modeling of the invariant part of a medical linear accelerator. In this method, instead of segmentation of scoring plane and analysis of phase space file, the mirror image ...
I Jabbari +3 more
doaj
Nanomaterial‐Based Precision Medicine for Breast Cancer Diagnosis and Treatment
This research emphasizes the use of targeted precision medicine in the treatment of breast cancer. Through the integration of diagnosis and therapeutic delivery, nanocarriers are designed to selectively target cancer cells, preserving healthy tissue, thereby improving treatment effectiveness and reducing side effects.
Tanaka Ndongwe +8 more
wiley +1 more source
ANALYSIS OF FAST NEUTRON TRANSPORT IN CHLORIDE SALTS USING MONTE CARLO METHOD
The aim of this paper is to present results of fast neutron behavior analysis within the chloride salts environment using simulations based on Monte Carlo method (MCNP 6.2).
Ondřej Šťastný +4 more
doaj +1 more source

