Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations

M. A. Uvakin; G. V. Alekhin; M. A. Bykov; S. I. Zaitsev

doi:10.3139/124.110700

Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations

Kerntechnik ◽

10.3139/124.110700 ◽

2016 ◽

Vol 81 (4) ◽

pp. 394-399 ◽

Cited By ~ 5

Author(s):

M. A. Uvakin ◽

G. V. Alekhin ◽

M. A. Bykov ◽

S. I. Zaitsev

Keyword(s):

Three Dimensional ◽

Kinetics Model ◽

Neutron Kinetics

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Space–time effects in the initiating phase of sodium fast reactors and their evaluation using a three-dimensional neutron kinetics model

Annals of Nuclear Energy ◽

10.1016/j.anucene.2015.04.033 ◽

2015 ◽

Vol 85 ◽

pp. 115-126 ◽

Cited By ~ 1

Author(s):

M. Guyot ◽

P. Gubernatis ◽

R. Le Tellier

Keyword(s):

Three Dimensional ◽

Space Time ◽

Kinetics Model ◽

Fast Reactors ◽

Time Effects ◽

Neutron Kinetics ◽

Sodium Fast Reactors

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A MOC-based neutron kinetics model for noise analysis

Annals of Nuclear Energy ◽

10.1016/j.anucene.2019.107070 ◽

2020 ◽

Vol 137 ◽

pp. 107070 ◽

Cited By ~ 1

Author(s):

A. Gammicchia ◽

S. Santandrea ◽

I. Zmijarevic ◽

R. Sanchez ◽

Z. Stankovski ◽

...

Keyword(s):

Noise Analysis ◽

Kinetics Model ◽

Neutron Kinetics

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Nodal neutron kinetics model based on nonlinear iteration procedure for LWR analysis

Annals of Nuclear Energy ◽

10.1016/s0306-4549(97)00078-9 ◽

1998 ◽

Vol 25 (8) ◽

pp. 507-528 ◽

Cited By ~ 19

Author(s):

Vyacheslav G. Zimin ◽

Hisashi Ninokata

Keyword(s):

Iteration Procedure ◽

Kinetics Model ◽

Neutron Kinetics ◽

Model Based ◽

Nonlinear Iteration

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Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh

Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory ◽

10.1115/icone22-31018 ◽

2014 ◽

Cited By ~ 1

Author(s):

Mingtao He ◽

Hongchun Wu ◽

Liangzhi Cao ◽

Youqi Zheng ◽

ShengCheng Zhou

Keyword(s):

Direct Method ◽

Three Dimensional ◽

Computational Time ◽

Neutron Kinetics ◽

Nodal Method ◽

Transport Code ◽

Geometry Configuration ◽

Nodal Transport ◽

Complicated Geometry ◽

Predictor Corrector

A space-time nodal transport code, DAISY, was developed to evaluate dynamic neutron behavior in innovative nuclear system. The steady transport process is based on an arbitrary triangles-z mesh nodal method which can treat complicated geometry configuration with enough precision and acceptable calculated quantity. This code employs the improved quasi-static method for neutron kinetics with a predictor-corrector scheme to improve computational efficiency. The direct method and the point approximation for neutron kinetics are also implemented into DAISY to evaluate the precision and efficiency of this predictor-corrector scheme. This code was verified by several transient benchmarks. It shows that the predictor-corrector scheme in DAISY can greatly reduce the computational time with enough precision.

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Recursive solutions for multi-group neutron kinetics diffusion equations in homogeneous three-dimensional rectangular domains with time dependent perturbations

Kerntechnik ◽

10.3139/124.110434 ◽

2014 ◽

Vol 79 (6) ◽

pp. 494-499 ◽

Cited By ~ 2

Author(s):

C. Z. Petersen ◽

B. E. J. Bodmann ◽

M. T. Vilhena ◽

R. C. Barros

Keyword(s):

Three Dimensional ◽

Time Dependent ◽

Diffusion Equations ◽

Neutron Kinetics ◽

Recursive Solutions

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RAMONA-4B a computer code with three-dimensional neutron kinetics for BWR and SBWR system transient - models and correlations

10.2172/576037 ◽

1998 ◽

Cited By ~ 2

Author(s):

U.S. Rohatgi ◽

H.S. Cheng ◽

H.J. Khan ◽

A.N. Mallen ◽

L.Y. Neymotin

Keyword(s):

Three Dimensional ◽

Computer Code ◽

Neutron Kinetics ◽

Transient Models

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Analytical estimations of pulse parameters in the modified integral neutron kinetics model for pulsed reactor and subcritical block

Izvestiya Wysshikh Uchebnykh Zawedeniy Yadernaya Energetika ◽

10.26583/npe.2016.2.09 ◽

2016 ◽

Vol 2016 (2) ◽

pp. 87-98

Author(s):

Andrej Vladislavovich Gulevich ◽

Oleg Filaretovich Kuharchuk ◽

Andrej Ivanovich Brezhnev

Keyword(s):

Kinetics Model ◽

Neutron Kinetics ◽

Pulse Parameters ◽

Pulsed Reactor ◽

Integral Neutron

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Analytical estimations of pulse parameters in the modified integral neutron kinetics model for pulsed reactor and subcritical block

Nuclear Energy and Technology ◽

10.1016/j.nucet.2016.07.007 ◽

2016 ◽

Vol 2 (3) ◽

pp. 191-196

Author(s):

A.V. Gulevich ◽

O.F. Kukharchuk ◽

A.I. Brezhnev

Keyword(s):

Kinetics Model ◽

Neutron Kinetics ◽

Pulse Parameters ◽

Pulsed Reactor ◽

Integral Neutron

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Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2021.103936 ◽

2021 ◽

Vol 141 ◽

pp. 103936

Author(s):

M. Rafiei ◽

G.R. Ansarifar ◽

K. Hadad ◽

M. Mohammadi

Keyword(s):

Nuclear Reactor ◽

Kinetics Model ◽

Feedback Effects ◽

Neutron Kinetics ◽

Load Following

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A Study on Regional Stability Analysis Methodology with a One-Point Neutron Kinetics Model

Nuclear Technology ◽

10.13182/nt99-a3030 ◽

1999 ◽

Vol 128 (2) ◽

pp. 257-275 ◽

Cited By ~ 24

Author(s):

Yutaka Takeuchi ◽

Yukio Takigawa ◽

Shiho Miyamoto

Keyword(s):

Stability Analysis ◽

Kinetics Model ◽

Regional Stability ◽

Neutron Kinetics ◽

Analysis Methodology

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