Analysis of models of an automatic power control system for a pressurized water reactor in dynamic mode with a change in the static control program
DOI:
https://doi.org/10.15276/opu.1.67.2023.08Keywords:
ACS, static control program, nuclear power unit core, approximation model, physical and mathematical modelAbstract
The process of decarbonization of the industry was intensified by the decision to include nuclear energy in the EU Green Taxonomy. The increase in the capacity of nuclear power plants and the attractiveness of this industry for a long time causes interest in the use of nuclear power plants for electricity dispatching. Thus, the development of an automatic control system for changing the power of nuclear power plants in dynamic modes becomes relevant. The energy release along the height of the reactor core under the action of xenon fluctuations is one of the problems in ensuring the safe operation and stability of the NPP power unit when the power level changes. Violation of the energy release safety criteria occurs when non-stationary transient xenon processes with positive feedback occur in the core. Within the framework of the automatic control theory, the modeling of the system and the control object is compiled on the basis of the use of physical and mathematical models. Transfer functions, structure and parameters of the control system are determined. As an alternative, it is proposed to use an approximation model of the process in the core. The model is presented on the basis of transformations in such a way that the results of the calculation on a certain interval coincide or are close to the results of the calculation when using the analytical model. Such a model can approximate a process that depends on two parameters: time and degree of load change. The results of changing the regulation of technological parameters by the automated power control system of nuclear power unit in dynamic mode, the model of which is based on an approximation or physical and mathematical model, were analyzed. The results of changing the parameters are obtained by comparing the results during the transition of control from one static program to another. Switching between static control programs was studied for such process parameters as coolant temperature at the entrance to the reactor core, average coolant temperature and steam pressure in the secondary circuit. The studies were carried out under the condition that the reactor power was reduced to 80 % during the operation of one control program and increased to 100% of the power when another static program was used in reverse.
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Jiang Q., Liu Y., Zeng W., Yu T. Study on switching control of PWR core power with a fuzzy multimodel. Annals of Nuclear Energy. 2020. 145. 107611. DOI: https://doi.org/10.1016/ j.anucene.2020.107611.
State-space model predictive control method for core power control in pressurized water reactor nuclear power stations / Wang G., Wu J., Zeng B., Xu Z., Wu W., Ma X. Nuclear Engineering and Technology. 2016. 49. 134–140. DOI: http://dx.doi.org/10.1016/j.net.2016.07.008.
Offset-cardinality phase diagram method of controlling reactor power / Aver’yanova S.P., Vokhmyanina N.S., Zlobin D.A., Filimonov P.E., Kuznetsov V.I., Lagovskii V.B. Atomic Energy. 2017. 121. 155–160. DOI: https://doi.org/10.1007/s10512-017-0176-5.
Comparison of Two Control Programs of the VVER-1000 Nuclear Power Unit Using Regression Data Mining Models / Foshch T., Machado J., Portela F., Maksimov M., Maksimova O. Nuclear and Radiation Safety. 2017. 3 (75). 11–17. DOI: https://doi.org/10.32918/nrs.2017.3(75).02.
Foshch T., Maksimov M., Pelykh S., Maksimova O. Models and methods for automated control of power change at VVER-1000 nuclear power unit. Nuclear and Radiation Safety. 2018. 1 (77). 24–30. URL: http://dspace.opu.ua/jspui/bitstream/123456789/10580/1/ydpb_2018_1_6.pdf.
Designing an automated control system for changing NPU energy release compensating for arising internal disturbing factors based on their approximation model / Brunetkin O., Beglov K., Maksymov M., Baskakov V., Vataman V., Kryvda V. Eastern-European Journal of Enterprise Technologies. 2022. 3 (2 (117)). 63–75. DOI: https://doi.org/10.15587/1729-4061.2022.258394.
Kokol E. A. Structural optimization of static power control programs for nuclear power plants with WWER-1000. Proceedings of Odessa Polytechnic University. 2015. 3 (47). 41–46. DOI: https://doi.org/ 10.15276/opu.3.47.2015.07.
A graph-theory-based dynamic programming planning method for distributed energy system planning: Campus area as a case study / Ding Y., Wang Q., Tian Z., Lyu Y., Li F., Yan Z., Xia X. Applied Energy. 2023. 329. 120258. DOI: https://doi.org/10.1016/j.apenergy.2022.120258.
Fathy E., Hassanien A. E. Fuzzy harmonic mean technique for solving fully fuzzy multilevel multiobjective linear programming problems. Alexandria Engineering Journal. 2022. 61 (10). 8189–8205. DOI: https://doi.org/10.1016/j.aej.2022.01.021.
Plakhotnuk А.А., Kokol Е. А., Maksimov М. V. Improved PCS software switch control power generating. Automation Technological and Business-Processes. 2015. 7 (3). 26–33. DOI: https://doi.org/10.15673/2312-3125.4/2015.50429.
Pelykh S. N., Maksimov M. V., Parks G. T. A method for VVER-1000 fuel rearrangement optimization taking into account both fuel cladding durability and burnup. Nuclear Engineering and Design. 2013. 257. 53–60. DOI: https://doi.org/10.1016/j.nucengdes.2012.12.022.
Maksymov M., Alyokhina S., Brunetkin O. Thermal and reliability criteria for nuclear fuel safety. River Publishers (Verlag). 2021. 260 p. e-ISBN: 9788770224000.
Maksimov M.V., Tsiselskaya T.A., Kokol E.A. The Method of Control of Nuclear Power Plant with VVER-1000 Reactor in Maneuverable Mode. Journal of Automation and Information Sciences. 2015. 47 (6). 17–32. DOI: https://doi.org/10.1615/JAutomatInfScien.v47.i6.20.
Modeling and control of nuclear reactor cores for electricity generation. A review of advanced technologies / Li G., Wang X., Liang B., Li X., Zhang B., Zou Y. Renewable and Sustainable Energy Reviews. 2016. 60. 116–128. DOI: https://doi.org/10.1016/j.rser.2016.01.116.
Maksimov M. V., Pelykh S. N., Gontar R. L. Principles of controlling fuel-element cladding lifetime in variable VVER-1000 loading regimes. Atomic Energy. 2012. 112 (4). 241–249. DOI: https://doi.org/10.1007/s10512-012-9552-3.
Foshch T., Portela F., Machado J., Maksimov M. Regression Models of the Nuclear Power Unit VVER-1000 Using Data Mining Techniques. Procedia Computer Science. 2016. 100. 253–262. DOI: https://doi.org/10.1016/j.procs.2016.09.151.
Robust power control design for a small pressurized water reactor using an H infinity mixed sensitivity method / Yan X., Wang P., Qing J., Wu S., Zhao F. Nuclear Engineering and Technology. 2020.52 (7). 1443–1451. DOI: http://doi.org/10.1016/j.net.2019.12.031.
Filimonov P. E., Aver'yanova S. P., Filimonova M. P. Control of control-rod groups in the maneuvering regime of VVÉR-1000 operation. Atomic Energy. 1998. 84 (5). 383–387. DOI: https://doi.org/ 10.1007/BF02414876.
Kokol. Е.А. Optimal power control of VVER-1000 due to targeted selection of the control program. Automation 2015: XXII International Conference on Automatic Control. Odessa: Ukraine. 2015. p. 119–120.
Plakhotnuk А. А., Kokol Е. А., Maksimov М. V. Simulation of changes in the structure of technical means of automation at the VVER-1000 while maneuvering. Automation Technological and Business-Processes. 2015. 7 (4). 64–71. DOI: https://doi.org/10.15673/2312-3125.24/2015.56334.
Ningbo L., Xueyao S. Research on the control of containment pressure of Gen II+ NPP under severe accident condition. Energy Procedia. 2017. 117. 220–224. DOI: https://doi.org/10.1016/ j.egypro.2017.08.098.
Zhou H., Pelykh S. N., Odrekhovska I. O., Maksymova O. B. Optimization of power control program switching for a WWER-1000 under transient operating conditions. Problems of Atomic Science and Technology. 2018. 1 (113). 218–221. URL: http://dspace.nbuv.gov.ua/bitstream/handle/123456789/ 137360/36-Zhou.pdf?sequence=1.
Pelykh S. N., Maksimov M. V., Ryabchikov S. D. The prediction problems of VVER fuel element cladding failure theory. Nuclear Engineering and Design. 2016. 302. 46–55. DOI: https://doi.org/ 10.1016/j.nucengdes.2016.04.005.
Pelykh S. N., Maksimov M. V., Nikolsky M. V. A method for minimization of cladding failure parameter accumulation probability in VVER fuel elements. Problems of Atomic Science and Technology. 2014. 92 (4). 108–116. URL: https://vant.kipt.kharkov.ua/ARTICLE/VANT_ 2014_4/article_2014_4_108.pdf.
Beglov K. V., Odrekhovska Y. O., Petik T. V., Vataman V. V. A method for searching the best static program for nuclear power unit control in the event of perturbations of different nature. Herald of Advanced Information Technology. 2023. 6 (2). 139–151. DOI: https://doi.org/10.15276/hait.06.2023.9.
Pelykh S. N., Maksimov M. V. Theory of VVER-1000 fuel rearrangement optimization taking into account both fuel cladding durability and burnup. Problems of Atomic Science and Technology. 2013. 44 (2) 84. 50–54. URL: http://dspace.nbuv.gov.ua/bitstream/handle/123456789/111678/08-Pelykh.pdf? sequence=1.
Pelykh S. N., Maksimov M. V. The method of fuel rearrangement control considering fuel element cladding damage and burnup. Problems of Atomic Science and Technology. 2013. 87 (5). 84–90. URL: https://vant.kipt.kharkov.ua/ARTICLE/VANT_2013_5/article_2013_5_84a.pdf.
Maksimov. M. V., Kanazirskyi. N. F., Kokol E. A. Control of the axial offset in a nuclear reactor at power maneuvering. Proceedings of Odessa Polytechnic University. 2014. 2 (4). 75–81. DOI: https://doi.org/10.15276/opu.2.44.2014.15.
Foshch T., Pelykh S. Improved models and method of power change of NPP unit with VVER-1000. Automation of Technological and Business–Processes. 2017. 9 (1). 56–66. DOI: http://dx.doi.org/10.15673/atbp.v9i1.505.
Odrekhovska Y. O., Zhou H., Pelykh S. N. Optimization of switching of static power control programs for NPPs with VVER-1000 in transient operating modes. XXIV Annual Scientific Conference of the Institute for Nuclear Research of the National Academy of Sciences of Ukraine: abstracts. Kiev: Ukraine. 2017. p. 123.
