Unraveling Unique Effect of Ergosterol on Lipid Membranes, and What We Can Do with the Future STS [PDF]
Ergosterol, a critical component of fungal membranes, has traditionally been thought to influence membrane properties in much the same way as cholesterol because of their similar structures.
Shuo Qian +4 more
doaj +2 more sources
Calculation of Thermal Neutron Diffusion Length in a Light Water Media using MCNP Code [PDF]
One of the key parameters of neutron diffusing media is the thermal neutron diffusion length. The popular calculational method is founded on utilizing MCNP code and curve fitting of a mathematical function to the neutron flux distribution in the media ...
M. Arkani
doaj +1 more source
Neutron Mean Free Path in the Slab Reactor Core using One-Dimensional Multi-group Diffusion Equation
Analysis of the neutron mean free path in the slab reactor core has been carried out using one-dimensional multi-group diffusion equation. This study aims to determine the neutron mean free path in the slab reactor core with the neutron diffusion ...
Putri Nabila +2 more
doaj +1 more source
The solution of the complex neutron diffusion equations system of equations in a spherical nuclear reactor is presented using the homotopy perturbation method (HPM); the HPM is a remarkable approximation method that successfully solves different systems ...
Mohammad Shqair +2 more
doaj +1 more source
The telegrapher's theory was used to develop a new formulation for the neutron noise equation. Telegrapher's equation is supposed to demonstrate a more realistic approximation for neutron transport phenomena, especially in comparison to the diffusion ...
Mona Bahrami, Naser Vosoughi
doaj +1 more source
Solution of neutron-transport multigroup equations system in subcritical systems [PDF]
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied.
Igor V. Shamanin +4 more
doaj +3 more sources
Development of the SH3-ACNEM Simulator Program in order to Solving the Forward and Adjoint neutron Diffusion Equation for Hexagonal Geometry Reactor Cores [PDF]
To perform a neutronic analysis of the reactor core, it is necessary to develop nuclear computing software to produce multi-group constants and numerical solutions to the multi-group neutron diffusion equation.
A. Kolali +2 more
doaj +1 more source
GEN-FOAM MODEL AND BENCHMARK OF DELAYED NEUTRON PRECURSOR DRIFT IN THE MOLTEN SALT REACTOR EXPERIMENT [PDF]
The effective delayed neutron fraction is an important reactor kinetics parameter. In flowing liquid-fuel reactors, this differs from the delayed neutron fraction because of the emission of delayed neutrons with a lower energy spectrum than prompt and ...
Shi Jun, Fratoni Massimiliano
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Development and Verification of Hexagonal Quasi-diffusion Code Based on Variational Nodal Method
New type reactors usually adopt advanced fuel types and more anisotropic fuel arrangements, the neutron spectrum is very different from that of pressurized water reactor, and the neutron anisotropy is stronger.
ZHUANG Kun;WANG Lianjie;LIU Kun;YAN Jiangtao;SHANG Wen
doaj
Impact of physical model error on state estimation for neutronics applications* [PDF]
In this paper, we consider the inverse problem of state estimation of nuclear power fields in a power plant from a limited number of observations of the neutron flux. For this, we use the Parametrized Background Data Weak approach.
Taumhas Yonah Conjungo +4 more
doaj +1 more source

