Results 51 to 60 of about 1,341 (152)
The effects of fuel type on control rod reactivity of pebble-bed reactor
As a crucial core physics parameter, the control rod reactivity has to be predicted for the control and safety of the reactor. This paper studies the control rod reactivity calculation of the pebble-bed reactor with three scenarios of UO2, (Th,U)O2, and ...
Zuhair +3 more
doaj +1 more source
Solidworks based MCNP6 reactor criticality calculation
Reactor criticality calculation is one of the key steps in nuclear reactor design and development. Los Alamos National Laboratory has developed some codes to perform these calculations. One of the codes is MCNP6 (Monte Carlo N-Particle).
Tumuluri, Madhuranath
core +1 more source
This study has been devoted to investigate the radiation shielding performance of epoxy-based micro and nano Bi2O3 and WO3 reinforced composites. While the research has been carried out by using experimental data and MCNP6 simulation for the micro ...
Yaşar Karabul, Orhan İçelli
doaj +1 more source
Abstract Purpose To develop clinically relevant test cases for commissioning Model‐Based Dose Calculation Algorithms (MBDCAs) for 192Ir High Dose Rate (HDR) gynecologic brachytherapy following the workflow proposed by the TG‐186 report and the WGDCAB report 372.
Vasiliki Peppa +6 more
wiley +1 more source
Performance of PMMA/Ta2O5 Composites as Medical Radiation Shielding: WinXCom and MCNP6 Studies
The growing reliance on radiation in contemporary applications underscores the imperative to safeguard individuals and the environment from harmful consequences.
Mustafa Çağlar
doaj +1 more source
Conceptual Design and Performance Assessment of the KORADIS System in South Korea
South Korea, currently operating 26 commercial nuclear reactors, is in need of establishing a permanent disposal solution for spent nuclear fuel (SNF) as the spent fuel pools approach their capacity. The enactment of the special act on high‐level radioactive waste (HLW) management in March 2025 and the second national basic plan have been formalized ...
Hyung-Ju Yun +4 more
wiley +1 more source
Optimization of airborne alpha beta detection system modeling using MCNP simulation
An airborne alpha beta detection system using passivated implanted planar silicon (PIPS) detector was modeled with the MCNP6 code and its resolution and detection efficiency were analyzed.
Si Hyeong Sung, Hee Reyoung Kim
doaj +1 more source
Novel concrete compositions for γ-rays and neutron shielding using WC and B4C
Concrete provides a superior shielding effect against γ-rays and neutron by reducing the radiation exposure to biological entities and their surroundings. A suitable amount of additives in the concrete mixture can enhance the shielding effect.
Bhargav K. Soni +7 more
doaj +1 more source
Abstract The production, attenuation, and absorption of secondary cosmic rays (SCR) are influenced by atmospheric parameters such as air pressure and temperature. To reliably correlate SCR flux measurements with atmospheric ionization driven by energetic particle precipitation, these dependencies must be quantified.
A. Al‐Qaaod +11 more
wiley +1 more source
MCNP calculations of neutron emission anisotropy caused by the GIT-12 hardware
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

