References
- H. SEKIMOTO, K. RYU, and Y. YOSHIMURA, “CANDLE: The New Burnup Strategy,” Nucl. Sci. Eng., 139, 3, 306 (2001); https://doi.org/10.13182/NSE01-01.
- H. SEKIMOTO, “A Review of CANDLE Burnup in Nuclear Reactors,” Int. J. Integr. Energy Syst., 1, 79 (2009).
- H. SEKIMOTO and M. YAN, “Design Study on Small CANDLE Reactor,” Energy Convers. Manage., 49, 7, 1868 (2008); https://doi.org/10.1016/j.enconman.2007.12.015.
- H. SEKIMOTO, “Application of CANDLE Burnup Strategy for Future Nuclear Energy Utilization,” Prog. Nucl. Energy, 47, 1–4, 91 (2005); https://doi.org/10.1016/j.pnucene.2005.05.007.
- J. A. KARIM, J. NISHIYAMA, and T. OBARA, “Application of Melt and Refining Procedure in the CANDLE Reactor Concept,” Ann. Nucl. Energy, 90, 275 (2016); https://doi.org/10.1016/j.anucene.2015.12.001.
- V. K. HOANG, J. NISHIYAMA, and T. OBARA, “Design Concepts of Small CANDLE Reactor with Melt-Refining Process,” Prog. Nucl. Energy, 108, 233 (2018); https://doi.org/10.1016/j.pnucene.2018.05.019.
- H. SEKIMOTO, “Application of ‘CANDLE’ Burn-Up Strategy to Several Reactors,” Proc. Advanced Reactors with Innovative Fuels, Chester, United Kingdom, October 22–24, 2001, p. 359, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (2002).
- S. NAKAYAMA, T. OKAWA, and H. SEKIMOTO, “Power Control of CANDLE Reactor by Coolant Flow Rate,” Prog. Nucl. Energy, 53, 7, 891 (2011); https://doi.org/10.1016/j.pnucene.2011.05.035.
- H. SEKIMOTO and S. NAKAYAMA, “Power Level Control of CANDLE Reactor Without Control Rods,” Ann. Nucl. Energy, 63, 427 (2014); https://doi.org/10.1016/j.anucene.2013.08.022.
- T. OKAWA, S. NAKAYAMA, and H. SEKIMOTO, “Design Study on Power Flattening to Sodium Cooled Large-Scale CANDLE Burning Core with Using Thorium Fuel,” Energy Convers. Manage., 53, 1, 182 (2012); https://doi.org/10.1016/j.enconman.2011.06.006.
- S. QVIST and E. GREENSPAN, “Design Space Analysis for Breed-and-Burn Reactor Cores,” Nucl. Sci. Eng., 182, 2, 197 (2016); https://doi.org/10.13182/NSE14-135.
- Y. NAGAYA et al., “MVP/GMVP Version 3: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods,” JAEA-Data Code 2016-018, Japan Atomic Energy Agency (2017).
- K. OKUMURA, Y. NAGAYA, and T. MORI, “MVP-BURN: Burn-Up Calculation Code Using a Continuous-Energy Monte Carlo Code MVP,” Draft Report for JAEA-Data/Code, Japan Atomic Energy Agency (2005).