DOI QR코드

DOI QR Code

Burnable Absorber Design Study for a Passively-Cooled Molten Salt Fast Reactor

  • Nariratri Nur Aufanni (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Eunhyug Lee (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Taesuk Oh (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Yonghee Kim (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
  • 투고 : 2023.06.30
  • 심사 : 2023.11.01
  • 발행 : 2024.03.25

초록

The Passively-Cooled Molten Salt Fast Reactor (PMFR) is one of the advanced design concepts of the Molten Salt Fast Reactor (MSFR) which utilizes a natural circulation for the primary loop and aims to attain a long-life operation without any means of fuel reprocessing. For an extended operation period, it is necessary to have enough fissile material, i.e., high excess reactivity, at the onset of operation. Since the PMFR is based on a fast neutron spectrum, direct implementation of a burnable absorber concept for the control of excess reactivity would be ineffective. Therefore, a localized moderator concept that encircles the active core has been envisioned for the PMFR which enables the effective utilization of a burnable absorber to achieve low reactivity swing and long-life operation. The modified PMFR design that incorporates a moderator and burnable absorber is presented, where depletion calculation is performed to estimate the reactor lifetime and reactivity swing to assess the feasibility of the proposed design. All the presented neutronic analysis has been conducted based on the Monte Carlo Serpent2 code with ENDF/B-VII.1 library.

키워드

과제정보

This work was supported by the National Research Foundation of Korea (NRF) Grant funded by the Korean Government (MSIP) (2021M2D2A2076383).

참고문헌

  1. Gen IV International Forum, Annual Report 2021, 2021. France. 
  2. T.J. Dolan, Molten Salt Reactor and Thorium Energy, Woodhead Publishing, United Kingdom, 2017. 
  3. J.C. Gehin, D.E. Holcomb, G.F. Flanagan, B.W. Patton, R.L. Howard, T.J. Harrison, Fast Spectrum Molten Salt Reactor Options, Office of Scientific and Technical Information (OSTI), 2011. 
  4. J. PARK, W. Choi, J. Lim, T. Oh, Y. Kim, Y. Yoon, S. Kim, S. Kim, in: Transactions of the Korean Nuclear Society Spring Meeting (South Korea, 2022. 
  5. S. Xu, T. Yu, J. Xie, L. Yao, Z. Li, Burnable poison selection and neutronics analysis of plate fuel assemblies, Front. Energy Res. 9 (2021). 
  6. S. HONG, S. Jang, T. Oh, Y. Kim, in: Transactions of the Korean Nuclear Society Virtual Spring Meeting (South Korea, 2021. 
  7. M. Hou, X. Zhou, B. Liu, Beryllium oxide utilized in nuclear reactors: Part I: application history, thermal properties, mechanical properties, corrosion behavior and fabrication methods, Nucl. Eng. Technol. 54 (12) (2022) 4393-4411. 
  8. M. Hou, X. Zhou, B. Liu, Beryllium oxide utilized in nuclear reactors: Part II: A systematic review of the neutron irradiation effects, Nucl. Eng. Technol. (2022). 
  9. K. Li, L. Qian, X. Li, Y. Ma, W. Zhou, BeO utilization in reactors for the improvement of extreme reactor environments - a review, Front. Energy Res. 9 (2021). 
  10. X.W. Zhou, Y.P. Tang, Z.M. Lu, J. Zhang, B. Liu, Nuclear graphite for high temperature gas-cooled reactors, New Carbon Mater. 32 (3) (2017) 193-204. 
  11. L.L. Snead, D. Sprouster, B. Cheng, N. Brown, C. Ang, E.M. Duchnowski, X. Hu, J. Trelewicz, Development and potential of composite moderators for elevated temperature nuclear applications, J. Asian Ceram. Soc. 10 (1) (2022) 9-32. 
  12. M. Wroblewska, ' D. Blanchet, A. Lyoussi, P. Blaise, J. Jagielski, Z. Marcinkowska, A. Boettcher, T. Machtyl, M. Januchta, I. Wilczek, A review and analysis of the state of the art on beryllium poisoning in research reactors, Ann. Nucl. Energy 163 (2021), 108540. 
  13. B. Cheng, E.M. Duchnowski, D.J. Sprouster, L.L. Snead, N.R. Brown, J.R. Trelewicz, Ceramic composite moderators as replacements for graphite in high temperature microreactors, J. Nucl. Mater. 563 (2022), 153591. 
  14. V.D. Davidenko, N.N. Ponomarev-Stepnoy, E. v Rodionova, V.F. Tsibulskiy, Important processes during fuel burnup in fast reactors with low excess reactivity, Atomic Energy 112 (6) (2012) 458-460. 
  15. J.R. Lamarsh, A.J. Baratta, Introduction to Nuclear Engineering, third ed., Prentice Hall, USA, 2001. 
  16. IAEA, in: Proceedings of a Technical Committee Meeting Held in San Carlos de Bariloche, Argentina, 15-19 November 1999 (Austria, 2002. 
  17. A. Kitamura, J. Matsumoto, Y. Furuyama, A. Taniike, N. Kubota, T. Ohsawa, K. Hashimoto, T. Horiguchi, T. Tsuruta, Measurements and analysis of neutron flux distribution in UTR-KINKI, J Nucl Sci Technol 40 (5) (2003) 349-355.