EDN: MIICNH
Authors & Affiliations
Bikeev A.S., Gyrevich M.I., Daichenkova Yu.S., Kalugin M.A., Prokhorov D.N., Shkarovsky D.A.
National Research Centre “Kurchatov Institute”, Moscow, Russia
Prokhorov D.N. – Research Engineer. Contacts: 1, Akademika Kurchatova pl., Moscow, Russia, 123182. Tel.: +7 (963) 500-90-32; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Bikeev A.S. – Head of Software Laboratory, Cand. Sci. (Tech.
Gyrevich M.I. – Chief Researcher, Dr. Sci (Phys.-Math.).
Daichenkova Yu.S. – Junior Researcher.
Kalugin M.A. – Depute Head of Scientific Director of the Kurchatov Nuclear Power Complex, Dr. Sci (Tech.).
Shkarovsky D.A. – Head of Division of Benchmark Calculations of Nuclear Reactors, Cand. (Phys. and Math.).
Abstract
Radiation service life of reactor vessel and internals is the maximum allowable time for safe operation from the point of view of brittle fracture. The radiation service life of reactor vessel and internals determine the time of safe operation of some NPP unit. Therefore, determining the fast neutron flux on the reactor pressure vessel and the reactor internals is an important task. An analysis of the sensitivity of the calculated results to the uncertainty of the initial data accepted in the calculation should be carried out to confirm the reliability of the calculated fluence. In the framework of the article the following parameters were considered: geometrical dimensions of core elements (diameter of central hole in pellet, pellet thickness, diameter of fuel rod, fuel assembly height), geometrical dimensions of vessel and internals (inside and outside diameter of the reactor pit, thickness of the anti-corrosion surfacing), operational parameters (coolant temperature at the core inlet, average coolant temperature at the core), mass of fuel in the assembly. As a result, the design uncertainty of the geometric dimensions of the in-vessel internals and reactor vessel make the greatest contribution to the value of the calculated fluence total error. It is shown that the uncertainty of the considered parameters leads to an equidistant change in fast neutron fluence, thus, the obtained values of the total relative errors can be introduced to all calculated values of the fast neutrons fluence on the inner surface of the baffle, reactor pit and reactor vessel.
Keywords
Monte Carlo, MCU, fluence, vessel, internals, baffle, reactor PIT, VVER-1000, sensitivity, radiation effect
Article Text (PDF, in Russian)
References
1. IAEA. PRIS. Power Reactor Information System. Available at: https://pris.iaea.org/PRIS/WorldStatistics/OperationalByAge.aspx (accessed 22.08.2023).
2. IAEA. Basic Safety Principles for Nuclear Power Plants 75-INSAG-3 Rev. 1. Vienna, 2015, pp. 114–115.
3. PNAE G-7-002-86 Normy raschyota na prochnost’ oborudovaniya i truboprovodov atomnyh energeticheskih ustanovok [PNAE G-7-002-86 Norms for calculating the strength of equipment and pipelines of nuclear power plants]. Moscow, Energoatomizdat Publ., 1989. 525 p.
4. Alekseev N.I., Bol’shagin S.N., Gomin E.A., Gorodkov S.S., Gurevich M.I., Kalugin M.A., Kulakov A.S., Marin S.V., Novosel’tsev A.P., Oleynik D.S., Pryanichnikov A.V., Sukhino-Khomenko E.A., Shkarovskiy D.A., Yudkevich M.S. Status MCU-5. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2011, no. 4, pp. 5–23.
5. Kalugin M.A., Oleynik D.S., Shkarovsky D.A. Overview of the MCU Monte Carlo software package. Annals of Nuclear Energy, 2015, vol. 82, pp. 54–62.
6. Ob’edinennyj vychislitel'nyj klaster NIC “Kurchatovskij institute” [Joint Computing Cluster of the National Research Center “Kurchatov Institute”]. Available at: http://computing.nrcki.ru/pages/main/index.shtml (accessed 22.08.2023).
7. Prezentaciya na temu: “Osobennosti konstrukcii TVS-2M (dlya RC, OYAB, OURR, CRR i operativnogo personala BSHCHU” [Presentation on the topic: “Features of the design of TVS-2M (for the RC, NSA, ORRM, TsRR and operational personnel of the control room”]. Pp. 7–12. Available at: https://ppt-online.org/54737 (accessed 22.08.2023).
8. Entsiklopediya ASU TP: Kontrollery, ustroystva vvoda-vyvoda, termopary [Encyclopedia of APCS: Controllers, input-output devices, thermocouples]. Available at: https:/bookasutp.ru/Chapter6_3_3.aspx (accessed 22.08.2023).
9. Leskin S.T., Shelegov A.S., Slobodchuk V.I. Fizicheskie osobennosti i konstrukciya reaktora VVER‑1000: Ucheb. Posobie dlya vuzov [Physical features and design of the VVER-1000 reactor. Textbook]. Moscow, 2011. Pp. 48–54.
10. Rezepov V.K., Denisov V.P., Kirilyuk N.A., Dragunov Yu.G., Ryzhov S.B. “Reaktory VVER-1000 dlya atomnyh elektrostancij. Sozdanie ustanovok VVER dlya ASE”. Podol'sk: Izdatel'stvo NPO “Gidropress” Publ. Pp. 184–200.
UDC 621.039.51...17
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, issue 3, 3:12
