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Stochastic Theory of Neutron Transport in Nuclear Reactor

Journal of Computational and Theoretical Transport, 2021
The work is an extended version of the report presented at the conference ICTT-26. In the Part I we derive the forward and backward time-dependent linear stochastic equations for probability densit...
R. Y. Nesterenko
semanticscholar   +4 more sources

SN transport method for neutronic noise calculation in nuclear reactor systems: Comparative study between transport theory and diffusion theory

Annals of Nuclear Energy, 2018
Abstract In this paper, the neutron noise based on transport theory and diffusion noise theory using Green’s function technique is calculated. As the neutron noise is used for core diagnostic, surveillance and monitoring, calculation of neutron noise precisely can play an important role in monitoring and safety.
Mona Bahrami, Naser Vosoughi
semanticscholar   +4 more sources

A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory

Nuclear science and engineering, 2021
This paper presents a new robust scheme for coupled physics nuclear reactor calculations. We focus specifically on high-fidelity whole-core transport calculations with coarse mesh finite difference (CMFD) coupled to thermal hydraulics.
Qicang Shen, B. Kochunas
semanticscholar   +1 more source

A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022
The variational nodal method (VNM) is an advanced nodal method in the field of reactor physics. The VNM solves neutron transport equations directly without transverse leakage interpolations used in other nodal methods.
Qizheng Sun   +4 more
semanticscholar   +1 more source

Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID

Nuclear science and engineering, 2022
The combined fission matrix (CFM) method is a newly developed neutron transport theory. This method estimates the fission matrix of the reactor core or spent fuel pool by combining a set of database fission matrices.
D. He, W. Walters
semanticscholar   +1 more source

Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022
In the reactor, the main purpose of radial shielding was to protect the internal structure and staff from radiation damage. The good shielding material must have both a high elastic scattering cross-section and a high absorption cross-section to reduce
Rui Li, Shichang Liu
semanticscholar   +1 more source

Numerical Simulation of Reactor Neutron Noise Based on Discrete Ordinate Finite Element Method

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022
At present, the technology of reactor neutron noise is developing rapidly, which can not only be used to measure some intrinsic parameters of the reactor core, but also be used for core fault diagnosis. The theoretical solution of reactor neutron noise
Bao-Xin Yuan   +9 more
semanticscholar   +1 more source

Precise localization of neutron noise sources based on transport theory and comparison with diffusion theory

, 2021
In an attempt to explore the significance of transport theory in neutron noise, localization of a noise source by Green’s function based on transport theory is investigated.
M. Bahrami, N. Vosoughi
semanticscholar   +1 more source

Methods of solving neutron transport equation

, 2021
The most fundamental task in the nuclear reactor analysis is to compute the neutron flux as a function of space, direction, energy, and time. The governing equation for this behavior is the complex neutron transport equation.
Anurag Gupta, S. Khan
semanticscholar   +1 more source

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