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Journal articles on the topic 'POINT REACTOR KINETICS'

Author: Grafiati

Published: 11 September 2023

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1

Planchard, J. "On the point-reactor kinetics approximation." Progress in Nuclear Energy 26, no. 3 (1991): 207–16. http://dx.doi.org/10.1016/0149-1970(91)90035-n.

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2

Abramov, B. D., and Yu V. Matveev. "Some Inverse Problems for Reactor Point Kinetics." Transport Theory and Statistical Physics 37, no. 2-4 (2008): 327–43. http://dx.doi.org/10.1080/00411450802515973.

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3

Aboanber, Ahmed E. "Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics." International Journal of Nuclear Energy 2013 (August 13, 2013): 1–12. http://dx.doi.org/10.1155/2013/903904.

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The base of reactor kinetics dynamic systems is a set of coupled stiff ordinary differential equations known as the point reactor kinetics equations. These equations which express the time dependence of the neutron density and the decay of the delayed neutron precursors within a reactor are first order nonlinear and essentially describe the change in neutron density within the reactor due to a change in reactivity. Outstanding the particular structure of the point kinetic matrix, a semianalytical inversion is performed and generalized for each elementary step resulting eventually in substantia

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4

Zhu, Wenzhang, and Qiang ZHAO. "ICONE19-43375 Solution of Point-Reactor Neutron Kinetics Equation by Gauss Precise Time-Integration Method." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19 (2011): _ICONE1943. http://dx.doi.org/10.1299/jsmeicone.2011.19._icone1943_160.

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5

Singh, Sudhansu, and Mohapatra Dinakrushna. "Solution of the reactor point kinetics equations by MATLAB computing." Nuclear Technology and Radiation Protection 30, no. 1 (2015): 11–17. http://dx.doi.org/10.2298/ntrp1501011s.

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The numerical solution of the point kinetics equations in the presence of Newtonian temperature feedback has been a challenging issue for analyzing the reactor transients. Reactor point kinetics equations are a system of stiff ordinary differential equations which need special numerical treatments. Although a plethora of numerical intricacies have been introduced to solve the point kinetics equations over the years, some of the simple and straightforward methods still work very efficiently with extraordinary accuracy. As an example, it has been shown recently that the fundamental backward Eule

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6

Hayes, J. G., and E. J. Allen. "Stochastic point-kinetics equations in nuclear reactor dynamics." Annals of Nuclear Energy 32, no. 6 (2005): 572–87. http://dx.doi.org/10.1016/j.anucene.2004.11.009.

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7

Obaidurrahman, Khalilurrahman, and Om Singh. "A comparative study of kinetics of nuclear reactors." Nuclear Technology and Radiation Protection 24, no. 3 (2009): 167–76. http://dx.doi.org/10.2298/ntrp0903167o.

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The paper deals with the study of reactivity initiated transients to investigate major differences in the kinetics behavior of various reactor systems under different operating conditions. The article also states guidelines to determine the safety limits on reactivity insertion rates. Three systems, light water reactors (pressurized water reactors), heavy water reactors (pressurized heavy water reactors), and fast breeder reactors are considered for the sake of analysis. The upper safe limits for reactivity insertion rate in these reactor systems are determined. The analyses of transients are

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8

Valocchi, G., J. Tommasi, and P. Ravetto. "Reduced order models in reactor kinetics: A comparison between point kinetics and multipoint kinetics." Annals of Nuclear Energy 147 (November 2020): 107702. http://dx.doi.org/10.1016/j.anucene.2020.107702.

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9

Kale, Vivek, Rakesh Kumar, K. Obaidurrahman, and Avinash Gaikwad. "Linear stability analysis of a nuclear reactor using the lumped model." Nuclear Technology and Radiation Protection 31, no. 3 (2016): 218–27. http://dx.doi.org/10.2298/ntrp1603218k.

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The stability analysis of a nuclear reactor is an important aspect in the design and operation of the reactor. A stable neutronic response to perturbations is essential from the safety point of view. In this paper, a general methodology has been developed for the linear stability analysis of nuclear reactors using the lumped reactor model. The reactor kinetics has been modelled using the point kinetics equations and the reactivity feedbacks from fuel, coolant and xenon have been modelled through the appropriate time dependent equations. These governing equations are linearized considering smal

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10

Nahla, Abdallah A., and Elsayed M. E. Zayed. "Solution of the nonlinear point nuclear reactor kinetics equations." Progress in Nuclear Energy 52, no. 8 (2010): 743–46. http://dx.doi.org/10.1016/j.pnucene.2010.06.001.

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11

Nahla, Abdallah A. "Analytical solution to solve the point reactor kinetics equations." Nuclear Engineering and Design 240, no. 6 (2010): 1622–29. http://dx.doi.org/10.1016/j.nucengdes.2010.03.003.

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12

Theler, Germán G., and Fabián J. Bonetto. "On the stability of the point reactor kinetics equations." Nuclear Engineering and Design 240, no. 6 (2010): 1443–49. http://dx.doi.org/10.1016/j.nucengdes.2010.03.007.

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13

Espinosa-Paredes, Gilberto, Marco-A. Polo-Labarrios, Erick-G. Espinosa-Martínez, and Edmundo del Valle-Gallegos. "Fractional neutron point kinetics equations for nuclear reactor dynamics." Annals of Nuclear Energy 38, no. 2-3 (2011): 307–30. http://dx.doi.org/10.1016/j.anucene.2010.10.012.

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14

Kulikov, Gennady G., Anatoly N. Shmelev, Vladimir A. Apse, and Evgeny G. Kulikov. "On a significant slowing-down of the kinetics of fast transient processes in a fast reactor." Nuclear Energy and Technology 6, no. 4 (2020): 295–98. http://dx.doi.org/10.3897/nucet.6.60379.

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The kinetics of nuclear reactors is determined by the average neutron lifetime. When the inserted reactivity is more than the effective delayed neutron fraction, the reactor kinetics becomes very rapid. It is possible to slow down the fast reactor kinetics by increasing the neutron lifetime. The authors consider the possibility of using the lead isotope, 208Pb, as a neutron reflector with specific properties in a lead-cooled fast reactor. To analyze the emerging effects in a reactor of this type, a point kinetics model was selected, which takes into account neutrons returning from the 208Pb re

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15

Ruščák, Marek, and Guido Mazzini. "PARCS/TRACE COUPLING METHODOLOGY FOR ROD EJECTION ON VVER 1000 REACTOR." Acta Polytechnica CTU Proceedings 4 (December 16, 2016): 80. http://dx.doi.org/10.14311/ap.2016.4.0080.

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The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper a methodology and a 3D kinetic model is prepared (PARCS), coupled with a thermal hydraulic system code (TRACE) for simulating this accident scenario for general VVER 1000 technology.

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16

Abramov, B. "CORRECTION OF INVERSE POINT KINETICS EQUATIONS FOR MEASUREMENT REACTIVITY IN THE PROMPT JUMP APPROXIMATION." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2019, no. 2 (2019): 151–59. http://dx.doi.org/10.55176/2414-1038-2019-2-151-159.

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We consider methods for calculating the reactivity of a nuclear reactor from the measured dependence of the neutron flux in the reactor on time, based on the use of the inverse point kinetics equations, which relate the values of reactivity and neutron flux in the reactor. The main attention is paid to the correction of the equations of inverse point kinetics in the prompt-jump approximation (or in the theory of singular perturbations for equations with a small parameter with the highest derivative). The nonequivalence of the corresponding problems for the direct and inverse point kinetics equ

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17

Suescún-Díaz, D., and G. Espinosa-Paredes. "On the numerical solution of the point reactor kinetics equations." Nuclear Engineering and Technology 52, no. 6 (2020): 1340–46. http://dx.doi.org/10.1016/j.net.2019.11.034.

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18

Hamada, Yasser Mohamed. "Trigonometric Fourier-series solutions of the point reactor kinetics equations." Nuclear Engineering and Design 281 (January 2015): 142–53. http://dx.doi.org/10.1016/j.nucengdes.2014.11.017.

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19

Nahla, Abdallah A., and Mohammed F. Al-Ghamdi. "Generalization of the Analytical Exponential Model for Homogeneous Reactor Kinetics Equations." Journal of Applied Mathematics 2012 (2012): 1–12. http://dx.doi.org/10.1155/2012/282367.

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Mathematical form for two energy groups of three-dimensional homogeneous reactor kinetics equations and average one group of the precursor concentration of delayed neutrons is presented. This mathematical form is called “two energy groups of the point kinetics equations.” We rewrite two energy groups of the point kinetics equations in the matrix form. Generalization of the analytical exponential model (GAEM) is developed for solving two energy groups of the point kinetics equations. The GAEM is based on the eigenvalues and the corresponding eigenvectors of the coefficient matrix. The eigenvalu

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20

R. Maleki, Bahram, Mehmet Tombakoglu, and Sedat Goluoglu. "Simulation of two-point reactor kinetics model of reflected reactors with Newtonian reactivity feedback." Annals of Nuclear Energy 177 (November 2022): 109315. http://dx.doi.org/10.1016/j.anucene.2022.109315.

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21

Nowak, Tomasz Karol, Kazimierz Duzinkiewicz, and Robert Piotrowski. "Numerical Solution of Fractional Neutron Point Kinetics Model in Nuclear Reactor." Archives of Control Sciences 24, no. 2 (2014): 129–54. http://dx.doi.org/10.2478/acsc-2014-0009.

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Abstract This paper presents results concerning solutions of the fractional neutron point kinetics model for a nuclear reactor. Proposed model consists of a bilinear system of fractional and ordinary differential equations. Three methods to solve the model are presented and compared. The first one entails application of discrete Grünwald-Letnikov definition of the fractional derivative in the model. Second involves building an analog scheme in the FOMCON Toolbox in MATLAB environment. Third is the method proposed by Edwards. The impact of selected parameters on the model’s response was examine

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22

Altahhan, Muhammad Ramzy, Ahmed E. Aboanber, Hanaa H. Abou-Gabal, and Mohamed S. Nagy. "Response of the point-reactor telegraph kinetics to time varying reactivities." Progress in Nuclear Energy 98 (July 2017): 109–22. http://dx.doi.org/10.1016/j.pnucene.2017.03.008.

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23

Aboanber, Ahmed E., and Abdallah A. Nahla. "Mathematical treatment for two-point reactor kinetics model of reflected systems." Progress in Nuclear Energy 105 (May 2018): 287–93. http://dx.doi.org/10.1016/j.pnucene.2018.02.015.

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24

Peinetti, F., C. Nicolino, and P. Ravetto. "Kinetics of a point reactor in the presence of reactivity oscillations." Annals of Nuclear Energy 33, no. 14-15 (2006): 1189–95. http://dx.doi.org/10.1016/j.anucene.2006.08.002.

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25

Hamieh, S. D., and M. Saidinezhad. "Analytical solution of the point reactor kinetics equations with temperature feedback." Annals of Nuclear Energy 42 (April 2012): 148–52. http://dx.doi.org/10.1016/j.anucene.2011.12.021.

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26

Luan, Xiuchun, and Pavel V. Tsvetkov. "Novel consistent approach in controllability evaluations of point reactor kinetics models." Annals of Nuclear Energy 131 (September 2019): 496–506. http://dx.doi.org/10.1016/j.anucene.2019.04.003.

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27

Espinosa-Paredes, G., and D. Suescún-Díaz. "Point reactor kinetics equations from P1 approximation of the transport equations." Annals of Nuclear Energy 144 (September 2020): 107592. http://dx.doi.org/10.1016/j.anucene.2020.107592.

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28

Zarei, Mohamad. "An enhanced formalism for the inverse reactor kinetics problem." Kerntechnik 87, no. 1 (2022): 66–71. http://dx.doi.org/10.1515/kern-2021-1008.

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Abstract The inverse kinetics problem in reactor physics is a standard formalism to unfold reactivity on the basis of registered power (flux) profile. The classical inverse point kinetics framework has been retrofitted herein to comprise thermal reactivity feedback effects. The instantaneous fuel and coolant temperatures are thus computed by way of the exponential time-differencing scheme and the corresponding thermal reactivity feedback is plugged into the inverse kinetics module. The core external reactivity is therefore unfolded employing only two consecutive time-steps of the power (flux)

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29

Cabrera, María I., Carlos A. Martín, Orlando M. Alfano, and Alberto E. Cassano. "Photochemical decomposition of 2,4-dichlorophenoxy acetic acid (2,4-D) in aqueous solution. I. Kinetic study." Water Science and Technology 35, no. 4 (1997): 31–39. http://dx.doi.org/10.2166/wst.1997.0079.

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The intrinsic kinetics of the photochemical decomposition of 2,4-dichlorophenoxyacetic acid in aqueous solution has been studied using light of 253.7 nm. Experiments were carried out in a well stirred batch reactor irradiated from its bottom by means of a tubular lamp and a parabolic reflector. Results were analyzed in terms of a very simple kinetic expression. Absorbed radiation effects were duly quantified by means of a one-dimensional radiation field model. This approach incorporates a variable absorption coefficient that is a function of the 2,4-D conversion. The decomposition kinetics can

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30

Yuferov, Anatoly G. "On the concept of “effective delayed neutron fraction”." Nuclear Energy and Technology 8, no. 4 (2022): 275–79. http://dx.doi.org/10.3897/nucet.8.96567.

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The article considers methodological issues related to the conceptual and terminological apparatus of the dynamics of nuclear reactors. Based on an elementary analysis of the standard point reactor kinetics equations, the author shows that it is necessary to clarify the physical meaning of the parameter β included in the equations, which is traditionally interpreted as the “effective delayed neutrons fraction” (EDNF). It follows directly from the kinetics equations that the parameter β, which appears in these equations as the EDNF, is, from the point of view of the neutron balance, the fractio

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31

Irkimbekov, Ruslan, Alexander Vurim, Galina Vityuk, Olzhas Zhanbolatov, Zamanbek Kozhabayev, and Artur Surayev. "Modeling of Dynamic Operation Modes of IVG.1M Reactor." Energies 16, no. 2 (2023): 932. http://dx.doi.org/10.3390/en16020932.

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This paper presents the results of a calculation code approach providing a solution to the point kinetics problem for the IVG.1M research reactor of the National Nuclear Center of the Republic of Kazakhstan and allowing the simulation of dynamic processes going on during reactor start-ups, including changes in the thermal state of all its elements, reactor regulator displacement, accumulation of absorbers in the fuel, and the beryllium reflector. A mathematical description of the IVG.1M point kinetics model is presented, which provides a calculation of the reactor neutron parameters, taking in

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32

Fan, Gen, and Wen Bin Liu. "An Integral Method for Solving the Point Reactor Neutron Kinetics Equations with Newtonian Temperature Feedback." Advanced Materials Research 732-733 (August 2013): 83–89. http://dx.doi.org/10.4028/www.scientific.net/amr.732-733.83.

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A numerical integral method to efficiently solve the point kinetics equations with Newtonian temperature feedback is described and investigated, which employs the better basis function (BBF) for the approximation of the neutron density in integral of one time step. The numerical evaluation is performed by the developed BBF code. The code can solve the general non-linear kinetics problems with six groups of delayed neutron. For the application purposes, the developed code and the method are tested by using a variety of problems, including ramp reactivity input with or without temperature feedba

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33

Leung, H. K. Y., and A. A. Harms. "Graph-theoretical basis of reactor point-kinetics / Graphentheoretische Grundlegung einer Reaktor-Punktkinetik." Kerntechnik 51, no. 3 (1987): 181–85. http://dx.doi.org/10.1515/kern-1987-510317.

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34

El-Genk, Mohamed S., and Jean-Michel P. Tournier. "A point kinetics model for dynamic simulations of next generation nuclear reactor." Progress in Nuclear Energy 92 (September 2016): 91–103. http://dx.doi.org/10.1016/j.pnucene.2016.07.007.

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35

Kinard, Matthew, and E. J. Allen. "Efficient numerical solution of the point kinetics equations in nuclear reactor dynamics." Annals of Nuclear Energy 31, no. 9 (2004): 1039–51. http://dx.doi.org/10.1016/j.anucene.2003.12.008.

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36

Li, Haofeng, Wenzhen Chen, Lei Luo, and Qian Zhu. "A new integral method for solving the point reactor neutron kinetics equations." Annals of Nuclear Energy 36, no. 4 (2009): 427–32. http://dx.doi.org/10.1016/j.anucene.2008.11.033.

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37

Nowak, Tomasz Karol, Kazimierz Duzinkiewicz, and Robert Piotrowski. "Fractional neutron point kinetics equations for nuclear reactor dynamics – Numerical solution investigations." Annals of Nuclear Energy 73 (November 2014): 317–29. http://dx.doi.org/10.1016/j.anucene.2014.07.001.

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38

Espinosa-Paredes, Gilberto. "Fractional-space neutron point kinetics (F-SNPK) equations for nuclear reactor dynamics." Annals of Nuclear Energy 107 (September 2017): 136–43. http://dx.doi.org/10.1016/j.anucene.2016.08.007.

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39

Espinosa-Paredes, Gilberto, and Carlos G. Aguilar-Madera. "Scaled neutron point kinetics (SUNPK) equations for nuclear reactor dynamics: 2D approximation." Annals of Nuclear Energy 115 (May 2018): 377–86. http://dx.doi.org/10.1016/j.anucene.2018.01.020.

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40

Giménez, Jaime, David Curcó, and Pilar Marco. "Reactor modelling in the photocatalytic oxidation of wastewater." Water Science and Technology 35, no. 4 (1997): 207–13. http://dx.doi.org/10.2166/wst.1997.0120.

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Two different experimental devices have been tested for the photocatalytic oxidation of phenol, by using TiO2 suspensions. At the laboratory level, experiments were carried out in microreactors with Xe lamps. At pilot plant scale, the experiments were done at the Plataforma Solar de Almería (PSA), Spain, by using a high concentrating radiation systems (Heliomans) and solar radiation. Both systems were characterized from the point of view of the radiation field. Kinetic experiments and radiation measurements showed that kinetics are first order with respect to the phenol concentration, and a li

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41

Schiassi, Enrico, Mario De Florio, Barry D. Ganapol, Paolo Picca, and Roberto Furfaro. "Physics-informed neural networks for the point kinetics equations for nuclear reactor dynamics." Annals of Nuclear Energy 167 (March 2022): 108833. http://dx.doi.org/10.1016/j.anucene.2021.108833.

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42

Kastanya, Doddy. "Evaluating the variations of point kinetics parameters in pressurized heavy water reactor analyses." Annals of Nuclear Energy 173 (August 2022): 109130. http://dx.doi.org/10.1016/j.anucene.2022.109130.

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43

Chen Wen-Zhen, Zhu Bo, and Li Hao-Feng. "The analytic solutions of point-reactor neutron-kinetics equation with small step reactivity." Acta Physica Sinica 53, no. 8 (2004): 2486. http://dx.doi.org/10.7498/aps.53.2486.

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44

Ganapol, Barry. "A refined way of solving reactor point kinetics equations for imposed reactivity insertions." Nuclear Technology and Radiation Protection 24, no. 3 (2009): 157–66. http://dx.doi.org/10.2298/ntrp0903157g.

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We apply the concept of convergence acceleration, also known as extrapolation, to find the solution of the reactor kinetics equations (RKEs). The method features simplicity in that an approximate finite difference formulation is constructed and converged to high accuracy from knowledge of the error term. Through the Romberg extrapolation, we demonstrate its high accuracy for a variety of imposed reactivity insertions found in the literature. The unique feature of the proposed algorithm, called RKE/R(omberg), is that no special attention is given to the stiffness of the RKEs. Finally, because o

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45

Diniz, Rodrigo Costa, Alessandro da Cruz Gonçalves, and Felipe Siqueira de Souza da Rosa. "Neutron point kinetics model with precursors’ shape function update for molten salt reactor." Nuclear Engineering and Design 360 (April 2020): 110466. http://dx.doi.org/10.1016/j.nucengdes.2019.110466.

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46

Nowak, Tomasz Karol, Kazimierz Duzinkiewicz, and Robert Piotrowski. "Numerical solution analysis of fractional point kinetics and heat exchange in nuclear reactor." Nuclear Engineering and Design 281 (January 2015): 121–30. http://dx.doi.org/10.1016/j.nucengdes.2014.11.028.

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47

Sosnovsky, Eugeny, and Benoit Forget. "Bond graph representation of nuclear reactor point kinetics and nearly incompressible thermal hydraulics." Annals of Nuclear Energy 68 (June 2014): 15–29. http://dx.doi.org/10.1016/j.anucene.2013.12.013.

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48

Altahhan, Muhammad Ramzy, Mohamed S. Nagy, Hanaa H. Abou-Gabal, and Ahmed E. Aboanber. "Formulation of a point reactor kinetics model based on the neutron telegraph equation." Annals of Nuclear Energy 91 (May 2016): 176–88. http://dx.doi.org/10.1016/j.anucene.2016.01.011.

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49

Ayyoubzadeh, Seyed Mohsen, and Naser Vosoughi. "On the limitations of linear power reactor noise analysis: A point kinetics approach." Annals of Nuclear Energy 102 (April 2017): 124–33. http://dx.doi.org/10.1016/j.anucene.2016.12.007.

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50

Behringer, K., and J. Piñeyro. "Concerning the stability parameter in point reactor kinetics driven by random reactivity noise." Annals of Nuclear Energy 21, no. 12 (1994): 787–91. http://dx.doi.org/10.1016/0306-4549(94)90025-6.

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