Optimisation of the control curves of load-changing nuclear power units taking into account thermal stress

Authors

  • Bálint Pudleiner HUN-REN Centre for Energy Research, Konkoly-Thege 29-33, Budapest H-1121, Hungary
  • Pál Szentannai Department of Energy Engineering, Faculty of Mechanical Engineering, Budapest University of Technology and Economics, Muegyetem 3, Budapest H-1111, Hungary
  • Lea Désesquelles Grenoble INP - Phelma, Graduate School of Engineering in Physics, Electronics, Materials Sciences, 3 Parvis Louis Néel, CS 50257, 38016 Grenoble Cedex 1, France
  • Camille Matter IMT Mines Albi, Ecole Nationale Supérieure des Mines d’Albi-Carmaux, Campus Jarlard, Cedex 09, Albi F-81013, France
  • Tamás Fekete HUN-REN Centre for Energy Research, Konkoly-Thege 29-33, Budapest H-1121, Hungary

DOI:

https://doi.org/10.24425/ather.2025.156835

Abstract

Besides the increasing share of uncontrollable renewables in the energy mix, the consumption/production balance of the grid must be permanently assured. Additionally, the successive stopping of traditional, fossil-fuelled power plants necessitates the controllability also of nuclear power plants. The major drawback of the load-following operation of such units is the side effect of load changes. They are, namely, carried out via non-stationary transitions, during which the temperature changes result in thermal stresses. The most critical, practically unchangeable part of the plant is the reactor pressure vessel, which is a thick-walled component of complex geometry. Hence, determining the optimal curves of the unit’s available control inputs is a crucial issue. For this, several tools are needed, such as a dynamical model of the entire power unit, a dynamical description of the thermal stress in the most critical points, a practical system of criteria of the optimisation condition, and numerical method for seeking the optimal pathway. The results demonstrate that optimised actuator trajectories can reduce thermally induced stress in the nozzle corner of the reactor pressure vessel during load-following operation.

References

1. Marusic, A., Loncar, D., Batelic, J., & Frankovic, V. (2016). Increasing flexibility of coal power plant by control system modifications. Thermal Science, 20(4), 1161–1169. doi:10.2298/TSCI160314159M

2. Raskovic, P.O., Cvetanovic, G., Vujanovic, M., Schneider, D.R., Guzovic, Z., Duic, N., & Oka, S.N. (2022). The progress toward more sustainable energy, water and environmental systems approaches and applications. Thermal Science, 26(5B), 4057–4066. doi:10.2298/TSCI2205057R

3. Ludwig, H., Salnikova, T., Stockman, A., & Waas, U. (2011). Load cycling capabilities of German nuclear power plants (NPP). VGB Powertech, 91(5), 38–44.

4. Grünwald, R., & Caviezel, C. (2017). Load-following capability of German nuclear power plants. Summary. KIT Library. https://publikationen.bibliothek.kit.edu/1000137922 [accessed 17 Jan. 2025].

5. Szentannai, P., Szűcs, T., Pudleiner, B., & Fekete, T. (2024). Transient phenomena and their consideration in load-following control of nuclear power plants. Thermal Science, 28(4B), 3183–3193. doi:10.2298/TSCI230805052S

6. Li, Y., Jin, T., Wang, Z., & Wang, D. (2020). Engineering critical assessment of RPV with nozzle corner cracks under pressurized thermal shocks. Nuclear Engineering and Technology, 52(11), 2638–2651. doi:10.1016/j.net.2020.04.019

7. Liu, R., Huang, M., Peng, Y., Wen, H., Huang, J., Ruan, C., Ma, H., & Li, Q. (2018). Analysis for crack growth regularities in the nozzle-cylinder intersection area of reactor pressure vessel. Annals of Nuclear Energy, 112, 779–793. doi:10.1016/j.anucene.2017.10.021

8. Trampus, P. (2024). Materials challenges of the new nuclear power plant in Hungary. Periodica Polytechnica Mechanical Engineering, 68(4), 328–335. doi:10.3311/PPme.37668

9. Rodriguez-Reyes, V.I., Abundez-Pliego, A., Petatan-Bahena, K.E., Miranda-Acatitlan, K.R., Colin-Ocampo, J., & Blanco-Ortega, A. (2024). Comparative evaluation of fatigue life estimation under variable amplitude loading through damage models based on entropy. Fatigue & Fracture of Engineering Materials & Structures, 47(6), 1584–1601. doi:10.1111/ffe.14262

10. Ray, A., Wu, M.K., Carpino, M., & Lorenzo, C.F. (1993). Damage-mitigating control of mechanical systems: Part I – Conceptual development and model formulation. Proceedings of the American Control Conference, 1172–1176, 2–4 June, San Francisco, USA. doi:10.23919/ACC.1993.4793051

11. Walter, H., & Epple, B. (Eds.) (2017). Numerical Simulation of Power Plants and Firing Systems (1st ed.). Springer. doi:10.1007/978-3-7091-4855-6

12. Corriou, J.-P. (2004). Dynamic modelling of chemical processes. In Process Control: Theory and Applications (pp. 3–75). Springer, London. doi:10.1007/978-3-319-61143-3_1

13. Rossi, I., Traverso, A., & Tucker, D. (2019). SOFC/Gas turbine hybrid system: A simplified framework for dynamic simulation. Applied Energy, 238, 1543–1550. doi:10.1016/j.apenergy.2019.01.092

14. Szentannai, P., Szűcs, T., Pudleiner, B., & Fekete, T. (2024). Transient phenomena and their consideration in load-following control of nuclear power plants. Thermal Science, 28(4B), 3183–3193. doi:10.2298/TSCI230805052S

15. Cheng, Y.T., Huang, M., Li, Y.D., Liu, W.Y., Wang, B., Meng, X., & Ouyang, X.P. (2023). Influence of interaction among multiple cracks on crack propagation in nozzle corner of reactor pressure vessel. Annals of Nuclear Energy, 194, 110142. doi:10.1016/j.anucene.2023.110142

16. Rabazzi, S.M., Albanesi, E.A., Nervi, J.E.R., & Signorelli, J.W. (2024). Highly detailed structural integrity assessment of the reactor pressure vessel nozzle of Atucha-I during a pressurized thermal shock event. Nuclear Engineering and Design, 418, 112905. doi:10.1016/j.nucengdes.2024.112905

17. The European Commission. (2016). Commission Regulation (EU) 2016/631 of 14 April 2016 establishing a network code on requirements for grid connection of generators. Official Journal of the European Union. https://eur-lex.europa.eu/eli/reg/2016/631/oj [accessed 17 Jan. 2025].

18. Bemporad, A., Ricker, N.L., & Morari, M. (2024). Model Predictive Control Toolbox User’s Guide. Release 2024b. MathWorks Help Center. https://www.mathworks.com/help/mpc/index.html [accessed 17 Jan. 2025].

19. Eslami, M.R., Hetnarski, R., Ignaczak, J., Noda, N., Sumi, N., & Tanigawa, Y. (2015). Theory of Elasticity and Thermal Stresses: Explanations, Problems and Solutions. Springer, Dordrecht. doi:10.1080/01495739.2013.846763

Downloads

Published

2025-12-30

How to Cite

Pudleiner, Bálint, et al. “Optimisation of the Control Curves of Load-Changing Nuclear Power Units Taking into Account Thermal Stress”. Archives of Thermodynamics, vol. 46, no. 4, Dec. 2025, pp. 41-48, doi:10.24425/ather.2025.156835.

Issue

Section

Articles

Similar Articles

<< < 16 17 18 19 20 21 22 23 24 25 > >> 

You may also start an advanced similarity search for this article.