Simulation of Pressurized Water Reactor to Find the Best Control Solution

2021;
: pp. 126 – 135
https://doi.org/10.23939/jeecs2021.02.126
Received: October 29, 2021
Revised: November 18, 2021
Accepted: December 17, 2021

T. Petik, V. Vataman, K. Beglov. Simulation of pressurized water reactor to find the best control solution. Energy Engineering and Control Systems, 2021, Vol. 7, No. 2, pp. 126 – 135. https://doi.org/10.23939/jeecs2021.02.126

1
Odessa Polytechnic State University
2
Odessa Polytechnic State University
3
Odessa Polytechnic State University

Since it is impossible to simultaneously control all technological and thermal parameters of the nuclear reactor, a vertically distributed model of a power unit was developed, which allows determining the axial offset and analyzing the behavior of thermal and neutron-physical processes of individual zones in core during boron control and movement of rods, as well as regulating the power of the nuclear reactor. For ten vertically distributed zones, neutrons and thermal processes in the reactor core were analyzed, as was the change of the axial offset during the discharge of the reactor load under the influence of the movement of the rods and the increase in the boric acid concentration. The purpose of this publication is to develop a vertically distributed model of the facility and use information technology to find the best solution for the control of a pressurized water reactor.

  1. Maksymov M. V., Tsiselskaya T. A., Kokol E. A. Method for controlling a reactor plant with WWER-1000 in maneuverable mode. Problems of Control and Informatics: Intern. scientific and technical journal. -2015. – No. 3. – p. 59 – 75. (in Russian)
  2. Severin V. P., Nikulina E. N., Lyutenko D. A., Bobukh E. Y. The problem of maneuverability of a nuclear power unit and the development of models of its control systems. Bulletin of the National Tech. University "Kharkov Polytechnic Institute". Kharkov: NTU “KhPI”, 2014. No. 61 (1103). p. 24 – 29. (in Russian)
  3. Verkhivker G. P., Kravchenko V. P. Fundamentals of calculation and design of nuclear power reactors / Ed. V. A. Dubkovsky. Odessa: TES, 2008. 409 pp. (in Russian)
  4. Ivanov V. A. Regulation of power units. L.: Mashinostroenie, 1982. 311 p. (in Russian)
  5. Borisenko V. I., Samoilenko D. V., Kadenko I. N. Peculiarities of some transient modes with load dropping on WWER-1000 // Atomic energy. T.115. Issue. 3. 2013. p. 132-136. https://doi.org/10.1007/s10512-013-9764-1 (in Russian)
  6. Nikulina E. N., Severin V. P., Lukidova D. A. Mathematical models for the study of transient modes of the WWER-1000 nuclear reactor of the V-320 series, 2018. No. 1(77). p. 18-23. https://doi.org/10.32918/nrs.2018.1(77).03 (in Russian)
  7. Andryushenko S. A., Afrov A. M., Vasiliev B. Y., Generalov V. N., Kosourov K. B., Semchenko Y. M., Ukraintsev V. F. NPP with WWER-type reactors 1000 M.: Logos, 2010. 604 p. (in Russian)
  8. Nikulina E. N., Severin V. P. Synthesis of optimal automatic control systems for a power unit in normal operating conditions // Nuclear and radiation safety. – 2013. – No. 3 (59). – P. 62 – 68. (in Russian)