EDN: BTTYLY
Authors & Affiliations
Ryazapov R.R., Mamaev A.V., Sobornov A.E., Kuskov A.M., Kudashkin I.A.
Nizhny Novgorod State Technical University n.a. R.E. Alekseev, Nizhny Novgorod, Russia
Ryazapov R.R. – Junior Researcher Assistant. Contacts: 24, st. Minina, Nizhny Novgorod, Russia, 603950. Tel.: +7 (952) 459-95-53; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Mamaev A.V. – Junior Researcher Assistant.
Sobornov A.E. – Junior Researcher Assistant.
Kuskov A.M. – Undergraduate.
Kudashkin I.A. – Undergraduate.
Abstract
Non-isothermal mixing of coolant flows occurring in the water-cooled reactor plants equipment is accompanied by thermal pulsations. The high intensity of temperature pulsations and caused temperature stresses, can lead to NPU equipment units metal fatigue. The active supercomputers development in recent decades makes it possible to obtain statistical and spectral-correlation characteristics of pulsations using numerical methods. However, the results of three-dimensional calculations by computational fluid dynamics codes require experimental confirmation. The experimental study of the single-phase coolant thermal hydraulic characteristics of a non-isothermal mixing in a Y-junction with “counter injection” is relevant.
The study was carried out in a hydraulically closed circuit. The experimental model is a Y-junction with “counter injection” of cool coolant. It consist of main and peripheral angled pipes. Model material – transparent organic glass. During the experiment, «cold» (temperature 20 °С) and “hot” (temperature 80 °С) coolant flows were mixed in the model. The mass flux of the “hot” flow was at the level of 174.4 kg/(s·m2), of the “cold” varied in range from 198.5 to 330.9 kg/(s·m2) with a step of 33.1 kg /(s·m2). The mixing process visualization was carried out by contrast tracer injection, with similar density into the model. The tracer injection was carried out sequentially at four different points, it is followed by a video recording with a frequency of 30 Hz.
In the study, a video samples were obtained, as well as synchronous experimental temperature fields with them. The vortex formation in the mixing zone is traced. The scales of vortices, time-averaged temperature profiles, temperature intensity profiles are determined. A total analysis of the hydrodynamics and temperature state of the flow made it possible to determine the main reasons of temperature pulsations in the frontal region before the peripheral pipe.
Keywords
temperature pulsations, thermal pulsations, non-isothermal mixing, resource, durability, thermal hydraulic characteristics, tracer, coolant, power plant, tee node
Article Text (PDF, in Russian)
References
- Abib E., Bergholz S., Rudolph J. German experiences in local fatigue monitoring. International Journal for Nuclear Power, 2013, vol. 58, pp. 284–289.
- Chapuliot S., Gourdin C., Payen T., Magnaud J.P., Monavon A. Hydro-thermal-mechanical analysis of thermal fatigue in a mixing tee. Nuclear Engineering and Design, 2005, vol. 235, pp. 575–596.
- Faidy C. High Cycle Thermal Fatigue: Lessons Learned From Civaux Event. Proc. of the Materials Reliability Program: Second International Conference on Fatigue of Reactor Components (MRP-84). Snowbird, Utah, July 29 – August 1, 2002.
- Sudakov A.V., Trofimov A.S. Pul'satsii temperatur i dolgovechnost' elementov energooborudovaniya [Temperature pulsations and durability of power equipment elements]. Leningrad, Energoatomizdat, Leningrad. otd. Publ., 1989. 176 p.
- Sudakov A.V., Trofimov A.S. Napryazheniya pri pul'satsiyakh temperature [Stresses at temperature pulsations]. Moscow, Atomizdat Publ., 1980. 64 p.
- Budov V.M., Dmitriev S.M.Forsirovannyye teploobmenniki YAEU [Forced heat exchangers of nuclear power plants]. Moscow, Energoatomizdat Publ., 1989. 174 p.
- Normy rascheta na prochnost' elementov oborudovaniya i truboprovodov dlya sudovykh atomnykh paroproizvodyashchikh ustanovok s vodo-vodyanymi reaktorami (NP-054-04) [Norms for calculating the strength of equipment elements and pipelines for ship nuclear steam generating plants with pressurized water reactors (NP-054-04)]. Rostekhnadzor of Russia, 2004.
- Jhung M.J. Assessment of thermal fatigue in mixing tee by FSI analysis. Nuclear Engineering and Technology, 2013, vol. 45, pp. 99–106.
- Mahaffy J., Chung B., Dubois F., Ducros F., Graffard E., Heitsch M., Henriksson M., Komen E., Moretti F., Morii T., Mühlbauer P., Rohde U., Scheuerer M., Smith B.L., Song C., Watanabe T., Zigh G. Best practice guidelines for the use of CFD in nuclear reactor safety applications. NEA/CSNI/R(2007) 5, 2007.
- Smith B.L. Assessment of CFD codes used in nuclear reactor safety simulations. Nuclear Engineering and Technology, 2010, vol. 42, pp. 339–364.
- Smith B.L., Andreani M., Bieder U., Ducros F., Graffard E., Heitsch M., Henrikkson M., Höhne T., Houkema M., Komen E., Mahaffy J., Menter F., Moretti F., Morii T., Mühlbauer P., Rohde U., Scheuerer M., Song C.H., Watanabe T., Zigh G. Assessment of CFD Codes for Nuclear Reactor Safety Problems – revision 2. OECD/NEA/CSNI/R(2014) 12, 2015.
- Smith B.L., Bestion D., Hassan Y. Experiments and CFD Code Applications to Nuclear Reactor Safety (XCFD4NRS). Special Issue: Nuclear Engineering and Design, 2010, vol. 240, pp. 2075–2382.
- Wakamatsu M., Nei H., Hashiguchi K. Attenuation of temperature fluctuations in thermal striping. Journal of Nuclear Science and Technology, 1995, vol. 32, pp. 752–762.
- Beaufils R., Courtin S. Analysis of the Father Experiment with an Engineering Method Devoted to High Cycle Thermal Fatigue. Proc. of the ASME 2011 Pressure Vessels & Piping Conference (PVP 2011). Baltimore, Maryland, USA, July 17–21, 2011.
- Bescherov D.E., Bolshukhin M.A., Kozin A.V., Lebedev V.V., Panov V.A., Pakhomov V.A., Sveshnikov D.N., Shishulin D.N., Legchanov M.A., Ryazapov R.R. Verifikatsiya metodiki rascheta ustalostnoy prochnosti oborudovaniya reaktornykh ustanovok pri nestatsionarnykh termotsiklicheskikh nagruzkakh [Verification of the methodology for calculating the fatigue strength of reactor plant equipment under nonstationary thermocyclic loads]. Trudy NGTU im. R.Ye. Alekseyeva [Proc. of NSTU im. R.E. Alekseeva]. 2019, no. 1 (124), pp. 81–91.
- Dmitriev S.M., Mamaev A.V., Ryazapov R.R., Sobornov A.E., Kotin A.V., Bolshukhin M.A., Bescherov D.E. Experimental studies of temperature pulsations during mixing of non-isothermal coolant flows in the elements of the equipment of the YARU. Izvestiya vysshikh uchebnykh zavedeniy. Yadernaya energetika, 2019, no. 2, pp. 117–127.
- Dmitriev S.M., Ryazapov R.R., Mamaev A.V., Sobornov A.E., Kotin A.V., Legchanov M.A., Lvov A.V. Izmereniye temperaturnogo i napryazhenno-deformirovannogo sostoyaniy trubnogo obraztsa pri vozdeystvii lokal'nykh stokhasticheskikh temperaturnykh pul'satsiy [Measurement of temperature and stress-strain states of a pipe sample under the influence of local stochastic temperature pulsations]. Pribory i metody izmereniy – Instruments and measurement methods, 2019, vol. 10, no. 1, pp. 53–60.
- Courtin S. High Cycle Thermal Fatigue Damage Prediction in Mixing Zones of Nuclear Power Plants: Engineering Issues Illustrated on the FATHER Case. Procedia Engineering, 2013, vol. 66, pp. 240–249.
- Miyoshi K., Kamaya M., Utanohara Y., Nakamura A. An investigation of thermal stress characteristics by wall temperature measurements at a mixing tee. Nuclear Engineering and Design, 2016, vol. 298, pp. 109–120.
- Braillard O., Edelin D. Advanced experimental tools designed for the assessment of the thermal load applied to the mixing tee and nozzle geometries in the PWR plant. Proc. of the Advancements in Nuclear Instrumentation, Measurement Methods and their Applications, ANIMMA 2009. Marseille, France, June 7–10, 2009.
- Chen M.S., Hsieh H.E., Ferng Y.M., Pei B.S. Experimental observations of thermal mixing characteristics in T-junction piping. Nuclear Engineering and Design, 2014, vol. 276, pp. 107–114.
UDC 621.039.534.25
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:17