Startseite Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme
Artikel
Lizenziert
Nicht lizenziert Erfordert eine Authentifizierung

Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme

  • Feriska Handayani Irka , Zaki Su’ud EMAIL logo , Dwi Irwanto , Siti Nurul Khotimah und Hiroshi Sekimoto
Veröffentlicht/Copyright: 17. August 2023
Veröffentlichen auch Sie bei De Gruyter Brill

Abstract

Design Study of Small Modular Gas-cooled Fast Reactors Employing Modified CANDLE Burnup with Radial Direction Shuffling Scheme has been performed with the power level 325–525 MWt. In this study Modified CANDLE burn-up scheme with radial direction shuffling has been employed with special attention to minimize reactivity swing during burn-up. The reactor cores are divided into 10 regions with equal volume in radial direction. The shuffling scheme of Modified CANDLE in radial direction can be described as follows. The natural uranium input is initially loaded in region 1. After 10 years of burnup the fuel in region 1 is shifter to region 2, the fuel in region 2 is shifted to region 3, etc. till the fuel of region 9 is shifter to region 10. The fuel from region 10 is taken out. Region 1–5 basically breeding zones in which plutonium is accumulated in fuels, while regions 5–10 have enough accumulated plutonium so that they contribute significantly to the power production. We call region 5–10 as burning zone. Nitride fuel is adopted as fuel in this study. Some parametric studies have been performed including variation of core height and power level. The neutronic calculations have been performed using the SRAC 2006 code with JENDL 4.0 nuclear data library. The optimized result shows the reactor could be operated 10 years continuously with maximum excess reactivity less than 1 % Δk/k for 500 MWt output power, 160 cm core active height and 110 cm core active radius.


Corresponding author: Zaki Su’ud, Department of Physics, Institut Teknologi Bandung, Bandung, Indonesia; and Department of Nuclear Science and Engineering, Institut Teknologi Bandung, Bandung, Indonesia, E-mail:

  1. Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.

  2. Research funding: This work has been supported by Indonesian Endowment Fund for Education (LPDP) and ITB research program of Ministry of research technology and higher education which is gratefully acknowledged.

  3. Conflict of interest statement: The authors declare no conflicts of interest regarding this article.

References

Ariani, M., SupardiJohan, A., Monado, F., Su’ud, Z., and Sekimoto, H. (2020). Optimized core design for small long-life gas cooled fast reactors with natural uranium-thorium-blend as fuel cycle input. J. Phy. Conf. Ser. 1568: 012015, https://doi.org/10.1088/1742-6596/1568/1/012015.Suche in Google Scholar

Ariani, M., Su’ud, Z., Waris, A., Asiah, N., and Ali, M. (2010). Effect of fuel fraction on small modified CANDLE burn-up based gas cooled fast reactors. AIP Conf. Proc. 1325: 249–252, https://doi.org/10.1063/1.3537909.Suche in Google Scholar

Ariani, M., Su’ud, Z., Monado, F., Waris, A., Khairurrijal, Arif, I., Ferhat, A., and Sekimoto, H. (2013). Optimization of small-long life gas cooled fast reactors with natural Uranium as fuel cycle input. Appl. Mech. Mater. 261–262: 307–311, https://doi.org/10.4028/www.scientific.net/amm.260-261.307.Suche in Google Scholar

Ariani, M., Su’ud, Z., Waris, A., KhairurrijalMonado, F., Sekimoto, H., and Nakayama, S. (2011). Design of small gas cooled fast reactor with two regions of natural uranium fuel fraction. AIP Conf. Proc. 1454: 69–72, https://doi.org/10.1063/1.4730690.Suche in Google Scholar

Duderstadt, J.J. and Hamilton, L.J. (1976). Nuclear reactor analysis. John Wiley & Sons, New Jersey, Hoboken.Suche in Google Scholar

Huang, J. and Jiang, J. (2022). The CANDLE burnup strategy applied to small modular pressurized water reactor loading with fully ceramic microencapsulated fuel. Kerntechnik 87: 158–166, https://doi.org/10.1515/kern-2021-0023.Suche in Google Scholar

IAEA (2012). IAEA nuclear energy series structural materials for liquid metal cooled fast reactor fuel assemblies – operational behaviour, 103. IAEA Nuclear Energy Series, Vienna, Austria.Suche in Google Scholar

Keisuke, O., Teruhiko, K., Kunio, K., and Keichiro, T. (2002). The comprehensive nuclear calculation code system (SRAC) JAERI report.Suche in Google Scholar

Monado, F., Ariani, M., Royani, I., and Su’ud, Z. (2020). Comparative study of conceptual design of gas-cooled fast reactor core type tall versus pan cake based on MCANDLE-B burn up strategy. J. Phy. Conf. Ser. 1568: 012013, https://doi.org/10.1088/1742-6596/1568/1/012013.Suche in Google Scholar

Monado, F., Su’ud, Z., Waris, A., Basar, K., Ariani, M., and Sekimoto, H. (2013). Application of modified candle burnup to very small-long life gas-cooled fast reactor. Adv. Mater. Res. 772: 501–506, https://doi.org/10.4028/www.scientific.net/amr.772.501.Suche in Google Scholar

Nagata, A., Takaki, N., and Sekimoto, H. (2009). A feasible core design of lead bismuth eutectic cooled CANDLE fast reactor. Ann. Nucl. Energ. 36: 562–566, https://doi.org/10.1016/j.anucene.2009.01.007.Suche in Google Scholar

Osato, H., Nishiyama, J., and Obara, T. (2018). Initial core design of CANDLE burning fast reactor using plutonium from LWR spent fuel. Ann. Nucl. Energy 120: 501–508, https://doi.org/10.1016/j.anucene.2018.06.015.Suche in Google Scholar

Pioro, I.L. (2016). Handbook of generation IV nuclear reactors. In: Handbook of generation IV nuclear reactors. Woodhead Publishing, Cambridge.10.1115/1.4035327Suche in Google Scholar

Rida, S.N.M. and Su’ud, Z. (2009). A design study of Pb-Bi-cooled fast reactors with natural uranium as the fuel cycle input. Int. J. Nucl. Energy Sci. Technol. 4: 217–222, https://doi.org/10.1504/ijnest.2009.027042.Suche in Google Scholar

Saadi, M.K., Abbaspour, A., and Pazirandeh, A. (2012). Annals of nuclear energy startup of “CANDLE” burnup in a gas-cooled fast reactor using Monte Carlo method. Ann. Nucl. Energy 50: 44–49, https://doi.org/10.1016/j.anucene.2012.07.019.Suche in Google Scholar

Seifritz, W. (2008). The analytical representation of the fundamental mode in 1-D-geometry for the CANDLE burn-up phenomenon. Kerntechnik 73: 75–77, https://doi.org/10.3139/124.100538.Suche in Google Scholar

Seifritz, W. (2009). Some affine solutions for CANDLE burn-up waves in 1D-geometry. Kerntechnik 74: 292–297, https://doi.org/10.3139/124.110040.Suche in Google Scholar

Seifritz, W. (2010). The boundary problem in the 1D-CANDLE burn-up reactor. Kerntechnik 75: 60–63, https://doi.org/10.3139/124.110055.Suche in Google Scholar

Sekimoto, H. and Miyashita, S. (2006). Startup of “Candle” burnup in fast reactor from enriched uranium core. Energ. Conv. Manag. 47: 2772–2780, https://doi.org/10.1016/j.enconman.2006.02.007.Suche in Google Scholar

Sekimoto, H. and Nagata, A. (2010). Performance optimization of the CANDLE reactor for nuclear energy sustainability. Energ. Conv. Manag. 51: 1788–1791, https://doi.org/10.1016/j.enconman.2009.12.045.Suche in Google Scholar

Sekimoto, H., Ryu, K., and Yoshimura, Y. (2001). CANDLE: the new burnup strategy. Nucl. Sci. Eng. 139: 306–317, https://doi.org/10.13182/NSE01-01.Suche in Google Scholar

Shibata, K., Iwamoto, O., Nakagawa, T., Iwamoto, N., Ichihara, A., Kunieda, S., Chiba, S., Furutaka, K., Otuka, N., Ohsawa, T., et al.. (2011). JENDL-4.0: a new library for nuclear science and engineering. Nucl. Sci. Technol. 48: 1–30, https://doi.org/10.1080/18811248.2011.9711675.Suche in Google Scholar

Su’ud, Z. and Sekimoto, H. (2008). Optimization of modified candle burnup scheme based long life Pb-Bi cooled fast Reactor with natural Uranium as fuel cycle input. Int. J. Nucl. Energy Sci. Technol. 7: 23–44, https://doi.org/10.1504/ijnest.2012.046983.Suche in Google Scholar

Su’ud, Z. and Sekimoto, H. (2013). The prospect of gas cooled fast reactors for long life reactors with natural uranium as fuel cycle input. Ann. Nucl. Energy 54: 58–66, https://doi.org/10.1016/j.anucene.2012.09.014.Suche in Google Scholar

Su’ud, Z., Ilham, M., Widiawati, N., and Sekimoto, H. (2018). Modified CANDLE burnup calculation system, its evolution, and future development. J. Phy. Conf. Ser. 1090: 012006, https://doi.org/10.1088/1742-6596/1090/1/012006.Suche in Google Scholar

Su’ud, Z., Irka, F.H., Imam, T.T., Sekimoto, H., and Sidik, P. (2013). Desain study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special shuffling strategy in radial direction. Adv. Mater. Res. 772: 530–535, https://doi.org/10.4028/www.scientific.net/amr.772.530.Suche in Google Scholar

Su’ud, Z., Miftasani, F., IlhamSarah, A., Ariani, M., Sekimoto, H., Waris, A., and Sidik, P. (2017). Design study of small modified CANDLE based long life gas cooled fast reactors. Energy Proc. 131: 6–14, https://doi.org/10.1016/j.egypro.2017.09.439.Suche in Google Scholar

Thomas, J., Anzieu, P., and Lenain, R. (2016). Chapter 11. The gas-cooled fast reactor. In: Nuclear reactor systems: a technical, historical and dynamic approach. EDP Sciences, Les Ulis, pp. 219–230.Suche in Google Scholar

Widiawati, N., Su’ud, Z., Irwanto, D., Permana, S., and Sekimoto, H. (2020a). Neutronic analysis of lead208-bismuth eutectic-cooled modified CANDLE reactor with core geometry variations neutronic analysis of lead 208-bismuth eutectic-cooled modified CANDLE reactor with core geometry variations. J. Phy. Conf. Ser. 1493: 012010, https://doi.org/10.1088/1742-6596/1493/1/012010.Suche in Google Scholar

Widiawati, N., Su’ud, Z., Irwanto, D., Permana, S., and Sekimoto, H. (2020b). Neutronic analysis of lead208-bismuth eutectic-cooled modified CANDLE reactor with core geometry variations neutronic analysis of lead 208-bismuth eutectic-cooled modified CANDLE reactor with core geometry variations. J. Phy. Conf. Ser. 1493, https://doi.org/10.1088/1742-6596/1493/1/012010.Suche in Google Scholar

Widiawati, N., Su’ud, Z., Irwanto, D., Permana, S., Takaki, N., and Sekimoto, H. (2020). Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant. Nucl. Eng. Technol. 53: 423–429, https://doi.org/10.1016/j.net.2020.07.008.Suche in Google Scholar

Zhang, D., Chen, X.N., Flad, M., Rineiski, A., and Maschek, W. (2013). Theoretical and numerical studies of TWR based on ESFR core design. Energy Convers. Manage. 72: 12–18, https://doi.org/10.1016/j.enconman.2013.01.037.Suche in Google Scholar

Zhang, D., Zheng, M., An, H., Chen, X., Tian, W., Qiu, S., and Su, G. (2014). Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor. Sci. China Technol. Sci. 57: 1229–1237, https://doi.org/10.1007/s11431-014-5514-4.Suche in Google Scholar

Zheng, M., Tian, W., Chu, X., Zhang, D., Qiu, S., and Su, G. (2014). Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core. Nucl. Eng. Des. 278: 679–685, https://doi.org/10.1016/j.nucengdes.2014.08.017.Suche in Google Scholar

Received: 2023-03-25
Published Online: 2023-08-17
Published in Print: 2023-10-26

© 2023 Walter de Gruyter GmbH, Berlin/Boston

Heruntergeladen am 27.9.2025 von https://www.degruyterbrill.com/document/doi/10.1515/kern-2023-0017/html
Button zum nach oben scrollen