Results 131 to 140 of about 10,040 (154)

Radiation dosimetry of 89Zr labeled antibody estimated using the MIRD method and MCNP code

Nuclear Engineering and Technology, 2023
Mahdi Sadeghi
exaly  

MCNP® Code Version 6.3.1 Release Notes

Michael Rising, Jerawan Armstrong, Simon Bolding, Jeffrey Bull, Alexander Clark, Cole Frederick, Jesse Giron, Avery Grieve, Wim Haeck, Fred Jones, Colin Josey, Joel Kulesza, Michael Lively, Sriram Swaminarayan, Jeremy Sweezy, Colin Weaver, Anthony Zukaitis   +16 more
openaire   +1 more source

Gamma ray shielding characteristics and exposure buildup factor for some natural rocks using MCNP-5 code

Nuclear Engineering and Technology, 2019
K G Mahmoud, M I Sayyed, Oleg L Tashlykov   +2 more
exaly  

Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment

Annals of Nuclear Energy, 2014
Wen-Xi Tian, Dalin Zhang, Yingwei Wu
exaly  

Evaluation of Radiation Shielding Features of Co and Ni-Based Superalloys Using MCNP-5 Code: Potential Use in Nuclear Safety

Applied Sciences (Switzerland), 2020
M I Sayyed, Faras Q Mohammed, K G Mahmoud   +2 more
exaly  

MCNP® Code Version 6.3.1: Build Guide (Rev. 1)

Jeffrey Bull, Colin Josey, Joel Kulesza, Michael Rising, Sriram Swaminarayan   +4 more
openaire   +1 more source

Study on gamma shielding polymer composites reinforced with different sizes and proportions of tungsten particles using MCNP code

Progress in Nuclear Energy, 2019
Hoda Alavian, Hossein Tavakoli-Anbaran
exaly  

MCNP® Code V.6.3.0 Unstructured-mesh Quality Metrics & Assessment

2022
openaire   +1 more source

MCNP® Code Version 6.3.0 Unstructured-mesh HDF5-based Output Verification

2022
openaire   +1 more source

Simulation studies for gamma ray shielding properties of Halloysite nanotubes using MCNP-5 code

Applied Radiation and Isotopes, 2019
M I Sayyed, K G Mahmoud, Erdem Şakar
exaly