

On the possibility of increasing the thermodynamic efficiency and nuclear fuel burn-up depth in VVER reactor
https://doi.org/10.15518/isjaee.2020.09.005
Abstract
Today, the global thermal power industry has already begun the transition to ultra-supercritical steam parameters, which makes it possible to increase the efficiency and reduce fuel consumption, and, accordingly, the discharge of harmful substances into the environment. NPPs need to increase their efficiency to maintain competitiveness in the electricity producer market. The following tasks are considered: increasing the installed capacity of operating power units by upgrading equipment, increasing the efficiency of NPPs by improving cycle arrangements and thermodynamic cycles, increasing the nuclear fuel burnup, increasing the installed capacity utilization factors (ICUF). The most common type of reactor in the nuclear power industry is the pressurized water reactor (VVER or PWR). A significant disadvantage of such reactors is the low value of the initial steam parameters (temperature and pressure). This is due to the temperature limitation equal to 350 °C for the cladding of fuel elements made of zirconium alloys. For this reason, the steam temperature in the second loop cannot exceed 315 °C. Thus, with an increase in the unit power of the units, the thermodynamic parameters of NPPs with reactors with pressurized water remain at the same level: the pressure of the primary circuit is ≈16 MPa, the temperature of the coolant at the outlet from the reactor is 320-330 °C; pressure and temperature of steam in the second loop, respectively, 6.3-7.2 MPa and 279-285 °C. The efficiency of modern NPPs with pressurized water reactors is at the level of 35%, which is lower than the efficiency of modern TPPs (45%), and significantly lower than the efficiency of steam-gas power plants (60%). One of the ways to increase the energy efficiency of NPPs with both light water and with a heavy water reactor is the improvement of the thermodynamic cycle. The paper presents the results of computer simulation of options for cycle arrangements of NPPs with a VVER-1200 reactor at reduced initial parameters using fossil-fired steam superheating, as well as steam compression to obtain ultra-supercritical steam parameters, and an assessment of the efficiency of using these cycle arrangements.
About the Authors
V. S. KostarevRussian Federation
Kostarev Vyacheslav Sergeevich - 5th year student at Ural Federal University, Department of Nuclear Power Plants and Renewable Energy Sources
19 Mira St., Yekaterinburg 620002
tel..: +79122963262
A. A. Anikin
Russian Federation
Anikin Aleksandr Alersandrovich - 5th year student at Ural Federal University, Department of Nuclear Power Plants and Renewable Energy Sources
19 Mira St., Yekaterinburg 620002
S. E. Shcheklein
Russian Federation
Shcheklein Sergey Evgenevich - Doctor of technical science, professor, head of Atomic Stations and Renewable Energy Sources Department at Ural Federal University
19 Mira St., Yekaterinburg 620002
References
1. Shchepetina T.D. O povyshenii KPD ehnergoblokov s vodo vodyanymi reaktorami (VVR) // Ehnergiya: ehkonomika, tekhnika, ehkologiya. – 2010. – №12 – c. 21-29
2. Atomnye ehlektrostantsii s reaktorami na bystrykh neitronakh s natrievym teplonositelem: uchebnoe posobie. V 2 ch. CH. 1 / A.I. Bel'tyukov, A.I. Karpenko, S.A. Poluyaktov, O.L. Tashlykov, G.P. Titov, A.M. Tuchkov, S.E. Shcheklein; pod obshch. red. S.E.Shchekleina, O.L. Tashlykova. – Ekaterinburg: URFU, 2013. – 548 s.
3. Vliyanie temperaturnykh kharakteristik na glubinu vygoraniya yadernogo topliva / Shcheklein S. E., Titov G. P., Borisova E. V. // Vestnik Odesskogo politekhnicheskogo universiteta. – 2011. – №2 (36) – s. 104-108
4. Rabota VVEHR-440 v rezhime prodleniya kampanii pri skol'zyashchem davlenii vo vtorom konture / Andrushechko S. A., Videneev E. N., Gorokhov V. F., Panin M. V., Petrov V. A., Proselkom V. N., Pytkin YU. N., Spasskov V. P. // Atomnaya ehnergiya. –1989. – №1 (66) – s. 3-6
5. Ispol'zovanie opyta Beloyarskoi AEHS v oblasti yadernogo peregreva pri sozdanii yadernykh reaktorov novogo pokoleniya s povyshennymi i sverkhkriticheskimi parametrami teplonositelya / Petrov A. A., Romenkov A. A., Yarmolenko O. A. // Izvestiya vuzov. Yadernaya ehnergetika. – 2009. – №2 – s. 21-29
6. Perspektivy ispol'zovaniya parogazovykh tekhnologii v ehnergoblokakh atomnykh ehlektrostantsii / Kasilov V. F., Nizovoi A. V. // Nauchnye issledovaniya: ot teorii k praktike. – 2015. – №4 (5) – s. 34-38
7. United Cycle. Rukovodstvo pol'zovatelya
8. Vliyanie temperatury neitronnogo gaza na prodolzhitel'nost' kampanii i vosproizvodstvo goryuchego v ehnergeticheskom reaktore / Krasin A. K., Minashin M. E., Sviridenko V. YA. // Atomnaya ehnergiya. – 1958. – T. 5, vyp. 2 – s. 111-118
9. Darwish M.A. Combining the nuclear power plant steam cycle with gas tur-bines / M.A. Darwish, F.M. Al Awadhi, A.O. Bin Amer // Energy. – 2010. – №35. – R. 4562–4571.
10. A Technology Roadmap for Generation IV Nuclear Energy Systems. Issued by the US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, December 2002.
11. K ispol'zovaniyu parogazovykh skhem dlya paroturbinnykh ustanovok na nasyshchennom vodyanom pare / Tsanev C.V., Belozerov S.N.// Izvestiya vuzov. Ehner-getika. – 1988. – №12. – S. 70–74.
12. Konstruktsiya uran-grafitovykh kanal'nykh reaktorov s trubchatymi tvehlami i yadernym peregrevom para / Dollezhal' N.A., Aleshchenkov P.N., Bulankov YU.V., Knyazeva R.D. // Atomnaya ehnergiya. – 1971. – №2 (30). – S.149-155.
13. Povyshenie ehnergoehffektivnosti AEHS / Shcheklein S. E., Tashlykov O. L., Dubinin A. M. // Izvestiya vuzov. Yadernaya ehnergetika. – 2015. – №4. – S. 15-25.
14. Opredelenie ehnergeticheskogo ehffekta modernizatsii ehnergooborudovaniya i tekhnologicheskikh sistem AEHS / Khomenok L. A., Kruglikov P. A., Smolkin YU. V., Sokolov K. V. // Teplotekhnika. – 2012. – №12. – S. 21-29.
15. Povyshenie ehffektivnosti ehks-pluatatsii ehnergoblokov AEHS s VVEHR-1000 putem modernizatsii teplovykh skhem / Khrustalev V. A., Novikova Z. YU. // Vestnik Saratovskogo gosudarstvennogo tekhnicheskogo universiteta. – 2011. – №3 (54). – S. 166-173.
16. Puti sovershenstvovaniya paroturbinnykh ustanovok AEHS / Filippov G. A., Nazarov O. I., Belyaev L. A. // Izvestiya Tomskogo politekhnicheskogo universiteta. – 2012. – №4. – S. 5-9.
17. Termodinamicheskie tsikly AEHS, rabotayushchikh na supersverkhkriticheskikh parametrakh vody / Abdulkadyrov V. M., Bogoslovskaya G. P., Grabezhnaya V. A. // Izvestiya vuzov. Yadernaya ehnergetika. – 2012. – №4. – S. 85-91.
18. Dolgov V. V. Ehnergobloki na osnove VVEHR s zakriticheskimi parametrami teplonositelya // Atomnaya ehnergiya. – 2002. – №4. – S. 277-280.
19. Vozmozhnosti povysheniya ehkonomichnosti i nadezhnosti parovykh turbin AEHS. / Filippov G. A., Yurchevskii E. B. // Teploehnergetika. – 2018. – №9. – S. 5-13.
20. Teplogidravlicheskie modeli oborudovaniya atomnykh stantsii / Avetisyan A. R., Pashchenko A. F., Pashchenko F. F. i dr. // M.: Fizmatlit, 2014. – 448 s.
Review
For citations:
Kostarev V.S., Anikin A.A., Shcheklein S.E. On the possibility of increasing the thermodynamic efficiency and nuclear fuel burn-up depth in VVER reactor. Alternative Energy and Ecology (ISJAEE). 2020;(25-27):52-61. (In Russ.) https://doi.org/10.15518/isjaee.2020.09.005