Results 131 to 140 of about 25,910 (172)
Some of the next articles are maybe not open access.
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018
In this paper the application of the virtual element method (VEM) to the multigroup, neutron diffusion equation will be presented. The VEM is a recently developed Bubnov-Galerkin spatial discretisation method based largely on the mimetic finite ...
J. Ferguson, J. Kópházi, M. D. Eaton
semanticscholar +1 more source
In this paper the application of the virtual element method (VEM) to the multigroup, neutron diffusion equation will be presented. The VEM is a recently developed Bubnov-Galerkin spatial discretisation method based largely on the mimetic finite ...
J. Ferguson, J. Kópházi, M. D. Eaton
semanticscholar +1 more source
Annals of Nuclear Energy, 2019
This paper proposes a new method for solving the time-dependent neutron transport equation based on nodal discretization using the MCNPX code. Most valid nodal codes are based on the diffusion theory with differences in approximating the leakage term ...
Meysam Ghaderi Mazaher +2 more
semanticscholar +1 more source
This paper proposes a new method for solving the time-dependent neutron transport equation based on nodal discretization using the MCNPX code. Most valid nodal codes are based on the diffusion theory with differences in approximating the leakage term ...
Meysam Ghaderi Mazaher +2 more
semanticscholar +1 more source
A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018Deep penetration problems exist widely in reactor applications, such as SPRR300 (Swimming Pool Research Reactor 300), a light water moderated, enriched uranium fueled research reactor in China. Deterministic transport theory is intrinsically suitable for
Wankui Yang +5 more
semanticscholar +1 more source
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018
Until recently, interior penalty methods have been applied to elliptic operators using an approach based on the mass matrix of finite elements that possess a constant Jacobian.
S. G. Wilson +3 more
semanticscholar +1 more source
Until recently, interior penalty methods have been applied to elliptic operators using an approach based on the mass matrix of finite elements that possess a constant Jacobian.
S. G. Wilson +3 more
semanticscholar +1 more source
Isogeometric Multi-Level Iterative Solution Algorithms With Applications in Nuclear Reactor Physics
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018The efficient solution of the neutron diffusion equation for large scale whole core calculations is of paramount importance; especially if the detailed pin-level power distribution and reaction rates are required.
C. Latimer, J. Kópházi, M. D. Eaton
semanticscholar +1 more source
Preliminary Neutron Simulation of Ceramic Fast Reactor
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018In this paper, preliminary neutron physical properties of ceramic fast reactor (CFR) are simulated and analyzed. The CFR core consists of ceramic materials, including nuclear fuels, coolants, structural materials, reflective and absorption materials ...
Xue-song Yan +4 more
semanticscholar +1 more source
Coupled Neutron and Gamma Heating Calculation Based on VARIANT Transport Solutions
Nuclear science and engineering, 2019For accurate assessment of nuclear heating in fast reactors, a new coupled neutron and gamma heating calculation scheme has been developed based on VARIANT nodal transport solutions of neutron and gamma flux distributions.
P. Deng, B. Jeon, H. Park, W. Yang
semanticscholar +1 more source
Methods and applications of 3-D SN neutron transport code ATES3
Life Cycle Reliability and Safety Engineering, 2023Anurag Gupta
semanticscholar +1 more source
CALCULATION OF THE PARAMETERS OF STOCHASTIC NEUTRON KINETICS IN ZERO POWER NUCLEAR REACTORS
PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS, 2019The majority of neutron-physical problems of nuclear power plants design can be solved on the basis of various approximations to the Boltzmann transport equation in terms of the averaged characteristics of the reactor: the effective multiplication factor,
E. Zemskov, K. Melnikov, I. Tormyshev
semanticscholar +1 more source
A re-visitation of space asymptotic theory in neutron transport
The European Physical Journal Plus, 2020S. Dulla, P. Ravetto
semanticscholar +2 more sources