scholarly journals ANALOG COMPUTING FOR A NEW NUCLEAR REACTOR DYNAMIC MODEL BASED ON A TIME-DEPENDENT SECOND ORDER FORM OF THE NEUTRON TRANSPORT EQUATION

2011 ◽  
Vol 43 (3) ◽  
pp. 243-256 ◽  
Author(s):  
Ahmad Pirouzmand ◽  
Kamal Hadad ◽  
Kune Y. Suh
Keyword(s):  
Transport Equation ◽  
Dynamic Model ◽  
Nuclear Reactor ◽  
Neutron Transport ◽  
Second Order ◽  
Time Dependent ◽  
Neutron Transport Equation ◽  
Order Form ◽  
Analog Computing ◽  
Reactor Dynamic

scholarly journals Numerical Approximation for Fractional Neutron Transport Equation

2021 ◽  
Vol 2021 ◽  
pp. 1-14
Author(s):  
Zhengang Zhao ◽  
Yunying Zheng
Keyword(s):  
Transport Equation ◽  
Nuclear Reactor ◽  
Neutron Transport ◽  
Transport Processes ◽  
Neutron Transport Equation ◽  
Spatial Direction ◽  
Fully Discrete ◽  
Discrete Methods ◽  
Fifth Order ◽  
Different Order

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 scheme is used in spatial direction and Runge–Kutta schemes are adopted in temporal direction. The linear stabilities of the generalized WENO5 schemes with different stages and different order ERK are discussed detailed. Numerical examples show the combinations of forward Euler/two-stage, second-order ERK and WENO5 are unstable and the three-stage, third-order ERK method with generalized WENO5 is stable and can maintain sharp transitions for discontinuous problem, and its convergence reaches fifth order for smooth boundary condition.

scholarly journals STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION

2021 ◽  
Vol 247 ◽  
pp. 03018
Author(s):  
P. Saracco ◽  
N. Abrate ◽  
M. Burrone ◽  
S. Dulla ◽  
P. Ravetto
Keyword(s):  
Transport Equation ◽  
Cross Sections ◽  
Eigenvalue Problems ◽  
Neutron Transport ◽  
Time Dependent ◽  
Neutron Transport Equation ◽  
Generalized Eigenvalue Problems ◽  
Time Dependent Problem ◽  
Steady State Solutions ◽  
Insight Into

The study of the steady-state solutions of neutron transport equation requires the introduction of appropriate eigenvalues: this can be done in various different ways by changing each of the operators in the transport equation; such modifications can be physically viewed as a variation of the corresponding macroscopic cross sections only, so making the different (generalized) eigenvalue problems non-equivalent. In this paper the eigenvalue problem associated to the time-dependent problem (α eigenvalue), also in the presence of delayed emissions is evaluated. The properties of associated spectra can give different insight into the physics of the problem.

HNsolutions of the time dependent linear neutron transport equation for a slab and a sphere

Kerntechnik ◽  
2007 ◽  
Vol 72 (1-2) ◽  
pp. 66-73 ◽  
Author(s):  
G. Türeci ◽  
M. C. Güleçyüz ◽  
C. Tezcan
Keyword(s):  
Transport Equation ◽  
Neutron Transport ◽  
Time Dependent ◽  
Neutron Transport Equation
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