Results 1 to 10 of about 80,518 (195)
Numerical Approximation for Fractional Neutron Transport Equation [PDF]
Journal of Mathematics, 2021 Fractional neutron transport equation reflects the anomalous transport processes in nuclear reactor. In this paper, we will construct the fully discrete methods for this type of fractional equation with Riesz derivative, where the generalized WENO5 ...
Zhengang Zhao, Yunying Zheng
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Monte Carlo Methods for the Neutron Transport Equation [PDF]
SIAM/ASA Journal on Uncertainty Quantification, 2022 This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [arXiv:1809.00827v2], [arXiv:1810.01779v4] and [arXiv:1901.00220v3], which describes the flux of neutrons through inhomogeneous fissile medium. Our aim is to analyse existing and novel Monte Carlo (MC) algorithms, aimed at simulating the lead eigenvalue ...
Alexander M. G. Cox +3 more
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ANALYSIS OF TIME-EIGENVALUE AND EIGENFUNCTIONS IN THE CROCUS BENCHMARK [PDF]
EPJ Web of Conferences, 2021 Time-dependent neutron transport in non-critical state can be expressed by the natural mode equation. In order to estimate the dominant eigenvalue and eigenfunction of the natural mode, CEA had extended the α-k method and developed the generalized ...
Nauchi Yasushi +2 more
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Influence of the spatial grid type on the result of calculating the neutron fields in the nuclear power plant shielding [PDF]
Nuclear Energy and Technology, 2023 The paper considers the influence of the spatial grid type on the result of solving the equation of neutron transport in the nuclear power plant (NPP) shielding.
Olga V. Nikolaeva +4 more
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Implementation of the time dependent neutron transport algorithm in 2D utilizing modular ray tracing by method of characteristic framework [PDF]
مجله علوم و فنون هستهای, 2023 This paper discusses the implementation of an algorithm for solving 2D time-dependent neutron transport equations in heterogeneous media. A novel modular ray tracing algorithm where neutrons are allowed to travel a longer path before being removed from ...
S. Ghaseminejad +3 more
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Variational nodal methods for neutron transport: 40 years in review
Nuclear Engineering and Technology, 2022 The variational nodal method for solving the neutron transport equation has evolved over 40 years. Based on a functional form of the Boltzmann neutron transport equation, the method now comprises a complete set of variants that can be employed for ...
Tengfei Zhang, Zhipeng Li
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Transport theory and systems theory [PDF]
Nuclear Technology and Radiation Protection, 2005 The simulation of singular nonlinear transport equation is obtained via corresponding neutron or photon kinetic equation. The conditions for convergence of the non stationary transport process to ward the pure dif fusion across the equilibriums are ...
Rastović Danilo
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A ROBUST SECOND-ORDER MULTIPLE BALANCE METHOD FOR TIME-DEPENDENT NEUTRON TRANSPORT SIMULATIONS [PDF]
EPJ Web of Conferences, 2021 A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problems is introduced and investigated. TDMB consists of solving two coupled equations: (i) the original balance equation (the transport equation integrated ...
Variansyah Ilham +2 more
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Multi-species Neutron Transport Equation [PDF]
Journal of Statistical Physics, 2019 The Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous fissile medium. Whilst well treated in the nuclear physics literature (cf. [9, 27]), the NTE has had a somewhat scattered treatment in mathematical literature with a variety of different approaches (cf. [8, 25]).
Alexander M. G. Cox +3 more
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Brazilian Journal of Radiation Sciences, 2021 This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares +2 more
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