Generate QR code
Open Access
Subscription Access
Structural integrity assessment and lifetime prediction for the control rods couplings of the WWER-440 reactor. Part 2. Assessment of the coupling structural integrity and justification of its material degradation monitoring interval
https://doi.org/10.22349/1994-6716-2021-105-1-163-176
Abstract
The structural integrity of the control rods couplings of the WWER-440 reactor is analyzed. On the basis of material investigation of the control rod couplings (martensitic-ferritic stainless steel grade 14Kh17N2, analogue of AISI 431 steel) that were under operation in the Unit 3 of Novovoronezh NPP it is shown that the structural integrity of the coupling is satisfied until the radiation-induced hardening of its material does not exceed 423 units of Vickers hardness.
Supporting agencies: This article has been prepared as a result of summarizing the studies carried out under the project No 375123 “Investigation of the main mechanical properties and characteristics of fracture resistance of the base metal and metal of welded joints of the elements of the reactor plant No 3 of NVO NPP to support R&D on material science substantiation of the extension of the service life of NPP equipment with WWER-440 to 60 years”, financed by Rosenergoatom Concern JSC.
About the Authors
A. J. Minkin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Minkin A. J.,
49 Shpalernaya St, 191015
B. Z. Margolin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Margolin B. Z., Dr Sc (Eng)
49 Shpalernaya St, 191015
V. G. Fedosov
PJSC Izhorskie Zavody
Russian Federation
Russian Federation
Fedosov V. G.
196650, Kolpino
References
1. Zverkov, V. V., Ignatenko, E. I., Yadernaya paroproizvodyashchaya ustanovka s VVER440 [Nuclear steam generating plant with VVER-440], Moscow: Energoatomizdat, 1987.
2. Shmelev, V.D., Dragunov, Yu.G., Denisov, V.P., Vasilchenko, I.N., Aktivnye zony VVER dlya atomnykh elektrostantsiy [VVER active zones for nuclear power plants], Moscow: Akademkniga, 2004.
3. Analysis of the operating conditions of the intermediate rod in the V-213 reactor and their effect on the service life, Podolsk: OKB Gidropress, 1982.
4. Standards for calculating the strength of equipment and pipelines of nuclear power plants. PNAE G-7-002–86, Moscow: Energoatomizdat, 1989.
5. Technical Conditions 108.11.853–87. Hot rolled and forged bars.
6. Margolin, B. Z., Gulenko, A.G., Fomenko, V.N., Kostylev, V. I., Dalneyshee razvitie modeli Prometey i metoda Unified Curve. Chast 2: Razvitie metoda Unified Curve [Further development of the Prometey model and the Unified Curve method. Part 2: Development of the Unified Curve method], Voprosy Materialovedeniya, 2016, No 4 (88), pp. 151–178.
7. ASTM E 1921-17a. Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range.
8. Vinokurov, V. F., Lapin, A. N., Odintsov, N. E., et al., Issledovanie sluzhebnykh svoistv materiala zakhvatov promshtang reaktorov tipa VVER-440 [Investigation of the service properties of the material of the grips of industrial rods of VVER-440 reactors], Proceedings of the 2nd International Scientific and Practical Conference “Problems of Materials Science in the Manufacture and Operation of NPP Equipment”, St Petersburg, 1992, V. 2.
Review
For citations:
Minkin A.J., Margolin B.Z., Fedosov V.G. Structural integrity assessment and lifetime prediction for the control rods couplings of the WWER-440 reactor. Part 2. Assessment of the coupling structural integrity and justification of its material degradation monitoring interval. Voprosy Materialovedeniya. 2021;(1(105)):163-176. (In Russ.) https://doi.org/10.22349/1994-6716-2021-105-1-163-176
Views:
250
Email this article 