EXPERIMENTAL STUDIES OF RADIATION HEATING OF MATERIALS DURING THEIR IRRADIATION IN THE IGR REACTOR
https://doi.org/10.52676/1729-7885-2025-4-159-167
Abstract
The paper presents experimental findings on the temperature measurement of structural material samples exposed to radiation heating during pulsed irradiation at the IGR research reactor. To record the temperature, an in-pile experimental device was specifically designed, consisting of a protective ampoule with an ultra-low-pressure environment to house the test samples. Thermocouples were embedded directly into the sample structures to enable precise temperature measurements within the materials. Temperature responses in 12 materials have been examined, including refractory metals, high-alloy steels, and aluminum alloys. Distinct heating patterns were identified that influenced by their physical and radiation properties of the materials. These results provide valuable data for refining thermal engineering models and enhancing the accuracy of calculations in the design of equipment for nuclear installations.
About the Authors
N. Ye. MukhamedovКазахстан
Kurchatov
G. A. Vityuk
Казахстан
Kurchatov
R. A. Irkimbekov
Казахстан
Kurchatov
S. A. Dolzhikov
Казахстан
Kurchatov
A. S. Surayev
Казахстан
Kurchatov
R. Ye. Kelsingazina
Казахстан
Kurchatov
Semey
References
1. J.L. Rempe, D.L. Knudson, J.E. Daw, K.G. Condie, S. Curtis Wilkins, New Sensors for In-Pile Temperature Measurement at the Advanced Test Reactor National Scientific User Facility, Nuclear Technology, Volume 175(3), pp. 681-691, 2011. https://doi.org/10.13182/NT11-A12515
2. B. Rossaert, T. Toyama, M. Yamazaki, K. Suzuki, M. Narui, T. Shikama, E. Sikik, P. Jacquet, S. Van Dyck, Development of a multipurpose rig for material irradiation tests in BR2, Journal of Nuclear Materials, Volume 565, 2022, 153742. https://doi.org/10.1016/j.jnucmat.2022.153742
3. Liu Chang, Xia Yi, Peng Xingjie, Zhao Wenbin, Song Jiyang, Jin Shuai, Liu Runqi, He Yuhao. Thermal Performance Analysis of Low Temperature Differential Flow Heat Transfer Process in HFETR Irradiation Device[J]. Nuclear Power Engineering, 2023, 44(S2): 184-187. https://doi.org/10.13832/j.jnpe.2023.S2.0184
4. A.V. Varivtsev, I.Yu. Zhemkov, A.V. Boev, O.V. Ishunina, Yu.V. Naboyshchikov, N.S. Poglyad, M.G. Sharonova, Computational and experimental study of an irradiation rig with a fuel heater for the BOR-60 reactor, Nuclear Energy and Technology, Volume 2, Issue 2, 2016, Pages 126-131. https://doi.org/10.1016/j.nucet.2016.05.010
5. C. Reynard-Carette, G. Kohse, J. Brun, M. Carette, A. Volte and A. Lyoussi, Review of Nuclear Heating Measurement by Calorimetry in France and USA, EPJ Web Conf., 170 (2018) 04019. https://doi.org/10.1051/epjconf/201817004019
6. Kee Nam Choo, Man Soon Cho, Sung Woo Yang, Byung Hyuk Jun, Myong Seop Kim, Development of a Low-Temperature Irradiation Capsule for Research Reactor Materials at HANARO, Nuclear Technology, Volume 195(2), pp. 213-221, 2016. https://doi.org/10.13182/NT15-154
7. A. Gusarov, K.L. Davis, J. Vande Pitte, B.J. Heidrich, I. Uytdenhouwen, S. Van Dyck, Monitoring the temperature of reactor experiments using radiation-induced swelling in SiC, Journal of Nuclear Materials, Volume 542, 2020, 152535. https://doi.org/10.1016/j.jnucmat.2020.152535
8. Hyun Ju Jin, Tae Kyu Kim, Neutron irradiation performance of Zircaloy-4 under research reactor operating conditions, Annals of Nuclear Energy, Volume 75, 2015, Pages 309-315. https://doi.org/10.1016/j.anucene.2014.08.042
9. M. Kiritani, The need for improved temperature control during reactor irradiation, Journal of Nuclear Materials, Volume 160, Issues 2–3, 1988, Pages 135-141. https://doi.org/10.1016/0022-3115(88)90040-2
10. Erlan Batyrbekov, Vladimir Vityuk, Alexander Vurim, Galina Vityuk, Experimental opportunities and main results of the impulse graphite reactor use for research in safety area, Annals of Nuclear Energy, 2023, Vol.182, 109582. https://doi.org/10.1016/j.anucene.2022.109582
11. Gorin, N. V., Kandiev, Ya. Z., Ul'yanov, A. I., Shmakov, D. V., Shcherbina, A. N., Gaidaichuk, V. A., Kaz'min, Yu. M., Skivka, A. S., Vasil'ev, A. P., & Pavshuk, V. A. (2001). Measurement of the temperature of structural materials heated by radiation from a pulsed uranium–graphite reactor. Atomic Energy, 90(1), 17–21. https://doi.org/10.1023/A:1011327604237
12. Vladimir Vityuk, Galina Vityuk, Alexander Vurim, Ruslan Irkimbekov, Ivan Kukushkin, Artur Surayev, Nurzhan Mukhamedov. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor // Progress in Nuclear Energy. –2023. – Volume 164, 104889. https://doi.org/10.1016/j.pnucene.2023.104889
13. Kelsingazina R., Vityuk V., Vurim A., Vityuk G., Mukhamedov N., Tikhomirov G. Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor // Annals of Nuclear Energy. –2024. –Vol.204, art. no. 110532. https://doi.org/10.1016/j.anucene.2024.110532
14. Kelsingazina R.E., Vityuk V.A., Vityuk G.A., Mukhamedov N.E., Dolzhikov S.A. Study of neutronic processes determining the nature of nuclear heating of materials in the impulse graphite reactor // NNC RK Bulletin. – 2024. – No. 3 (99). – P. 56–64. (In Russ.)] https://doi.org/10.52676/1729-7885-2024-3-56-64
15. Mukhamedov N.Ye., Vityuk V.A., Vityuk G.A., Vurim A.D., Kelsingazina R.Ye., Dolzhikov S.A., Zhengis D.T., Suraev A.S. Computational studies in support of possibility of conducting an in-pile experiment with power reactor fuel during the implementation of the long-term operation mode of the IGR reactor // NNC RK Bulletin. – 2024. – No. 4 (100). – P. 88–95. (In Russ.)] https://doi.org/10.52676/1729-7885-2024-4-88-95
16. Chirkin V.S. Teplofizicheskie svoystva materialov yadernoy tekhniki. Moscow: Atomizdat, 1968. – 395 p. (In Russ.)]
17. Bobkov V.P., Fokin L.R., Petrov E.E., Popov V.V., Rumiantsev V.N., Savvatimsky A.I. Thermophysical Properties of Materials for Nuclear Engineering: a Tutorial and Collection of Data. IAEA, VIENNA, 2008.
18. Неймарк Б.Е. Физические свойства сталей и сплавов, применяемых в энергетике, справочник. М.: Энергия, 1967. – 240 с.
19. Mughabghab S.F. Atlas of Neutron Resonances: Resonance Parameters and Thermal Cross Sections. Z = 1–100. 6th ed. Amsterdam: Elsevier, 2018. 1400 p.
20. Mughabghab S.F. Atlas of Neutron Resonances: Resonance Properties and Thermal Cross Sections, Z = 61–102. 6-е ed. Amsterdam: Elsevier, 2018. 696 p.
Supplementary files
Review
For citations:
Mukhamedov N.Ye., Vityuk G.A., Irkimbekov R.A., Dolzhikov S.A., Surayev A.S., Kelsingazina R.Ye. EXPERIMENTAL STUDIES OF RADIATION HEATING OF MATERIALS DURING THEIR IRRADIATION IN THE IGR REACTOR. NNC RK Bulletin. 2025;(4):159-167. (In Russ.) https://doi.org/10.52676/1729-7885-2025-4-159-167
JATS XML









