STUDI PENGARUH PERBEDAAN KETEBALAN FREEZE-VALVE DI MSR (MOLTEN SALT REACTOR) DALAM PENGENDALIAN KECELAKAAN
), Mustari A. P. A.(2), Irwanto D.(3), Permana S.(4), Pramuditya S.(5),
(1) Departemen Fisika - ITB
(2) Departemen Fisika - Instittut Teknologi Bandung
(3) Departemen Fisika - Institut Teknologi Bandung
(4) Departemen Fisika - Institut Teknologi Bandung
(5) Departemen Fisika - Institut Teknologi Bandung
Corresponding Author
Abstract
STUDI PENGARUH PERBEDAAN KETEBALAN FREEZE-VALVE DI MSR (MOLTEN SALT REACTOR) DALAM PENGENDALIAN KECELAKAAN. MSR merupakan sebuah tipe reaktor yang menggunakan bahan bakar cair, yakni garam cair yang sekaligus berfungsi sebagai pendinginnya. Meskipun MSR diakui unggul dari segi keamanan dan menjadi salah satu kandidat reaktor Generasi IV, namun dibutuhkan penelitian lebih lanjut untuk mencegah kecelakaan reaktor akibat peningkatan suhu bahan bakar cair. Sebuah freeze-valve merupakan salah satu sistem keamanan yang sangat berfungsi di MSR. Sebuah freeze-valve didesain untuk meleleh saat suhu bahan bakar mendekati titik leleh dinding reaktor dan membuka jalan bahan bakar menuju subcritical-tank. Sebuah eksperimen sederhana telah berhasil dilakukan pada penelitian ini untuk mempelajari mekanisme kerja freeze-valve tersebut. Penelitian ini dilakukan untuk menganalisa pengaruh perbedaan ketebalan pada freeze-valve (parafin) yang dialiri fluida panas bersuhu 800C. Variasi ketebalan yang digunakan adalah 10, 13, dan 20 mm dengan diameter yang sama, yaitu 23 mm. Berdasarkan variasi ketebalan tersebut ditemukan bahwa jika keadaan kecelakaan didesain pada saat suhu fluida di dalam tabung mencapai 800C, maka dibutuhkan sebuah freeze-valve dengan tebal 7 mm agar dapat terbuka dalam waktu 10 menit dan fluida dapat mengalir menuju subcritical tank.
Keywords
References
[1] H. G. MacPherson, "The Molten Salt Reactor Adventure," Nuclear Science and Engineering, vol. 90, no. 4, pp. 374-380, 1985.
[2] R. C. Robertson, "Conceptual Design Study of A Single-Fluid Molten Salt Breeder Reactor," Oak Ridge National Laaboratory, Oak Ridge, 1978.
[3] s. J and et.al, "The molten salt reactor (msr) in generation iv: Overview and perspectives," Progress, vol. 77, p. 308, 2014.
[4] C. Fiorina, M. Aufiero, A. Cammi, F. Franceschini, J. Krepel and L. Luzzi, "Investigation of the MSFR core physics and fuel cycle characteristics,," Progress in Nuclear Energy, vol. 68, pp. 153-168, 2013.
[5] B. E. Prince, S. J. Ball, J. R. Engel, P. N. Haubenreich and T. W. Kerlin, "Zero-Power Physics Experiment on The Molten-Salt Reactor Experiment," Oak Ridge National Laboratory, Oak Ridge, 1968.
[6] G. Grosch, "https://www.gen-4.org/gif/," 23 09 2013. [Online]. Available: https://www.gen-4.org/gif/jcms/c_9502/generation-iv-goals.
[7] D. Heuer, E. Merle-Lucotte, M. A. Allibert, M. Brovchenko, V. Ghetta and P. Rubiolo, "Towards the tkorium fuel cycle with molten salt fast reactors," Annal of Nuclear Energy, pp. 421-429, 2014.
[8] O. N. E. A. f. t. G. I. I. Forum, " Technology roadmap update for generation, GIF annual report," 2014.
[9] R. Sheu, C. Chao, O. Feynberg and Y.-W. Liu, "A fuel depletion analysis of the MSRE and three conceptual small molten-salt reactors for Mo-99 production," Annals of Nuclear Energy, vol. 71, pp. 111-117, 2014.
[10] D. Meneley and A. Muzumdar, "Power Reactor Safety Comparison - A Limited Review," in Proceedings of CNS 30th Annual Conferences, Calgary, 2009.
[11] Y. Ritsuo, K. Mitachi, Y. Shimazu and M. Kinoshita, "Safety Criteria and Guidlines for MSR Accident Analysis," PHYSOR, September 2014.
[12] C. Guerrieri, A. Cammi and L. Luzzi, "An approach to the MSR dynamics and stability analysis," Progress in Nuclear Energy, vol. 67, pp. 56-73, 2013.
[13] M. Richardson, "Development of Freeze Valve for use in the MSRE," (Report ORNL-TM-128). Oak Ridge National Laboratory, 1962.
[14] O. C. van den Bergh, Emergency drainage of the MSFR, Bachelor thesis, Delft University of Technology, 2016.
[15] M. B. e. al, "Design-related studies for the preliminary safety assessment of the molten," Nuclear science and engineering, vol. 175, p. 329, 2013.
[16] I. Koks, Melting behaviour of the freeze plug in a molten salt fast reacto, Delft University of Technology, 2016.
[17] V. Ignatiev and A. Surenkov, "Alloys compatibility in molten salt fluorides: Kurchatov Institute related experience," Journal of Nuclear Materials, vol. 441, pp. 592-603, 2013.
[18] A. Furutani, S. Imahori, K. Sato and M. Saito, "Erosion behavior of a slid plate by a liquid jet - Effect of molten layer," Nuclear Engineering and Design, pp. 153-169, 1991.
DOI: 10.17146/gnd.2021.24.1.5957
Copyright (c) 2021 GANENDRA Majalah IPTEK Nuklir
This work is licensed under a Creative Commons Attribution-NonCommercial-ShareAlike 4.0 International License.
.png)
