References
- B. H. YAN, “Review of the Nuclear Reactor Thermal Hydraulic Research in Ocean Motions,” Nucl. Eng. Des., 313, 3, 370 (2017); https://doi.org/https://doi.org/10.1016/j.nucengdes.2016.12.041.
- J. H. KIM et al., “Study on the Natural Circulation Characteristics of the Integral Type Reactor for Vertical and Inclined Conditions,” Nucl. Eng. Des., 207, 1, 21 (2001); https://doi.org/https://doi.org/10.1016/S0029-5493(00)00417-9.
- T. W. KIM et al., “Numerical Study on the Natural Circulation Characteristics in an Integral Type Marine Reactor for Inclined Conditions,” Nucl. Eng. Technol., 33, 4, 397 (2001).
- I. IYORI et al., “Natural Circulation of Integrated-Type Marine Reactor at Inclined Attitude,” Nucl. Eng. Des., 99, 87, 423 (1987); https://doi.org/https://doi.org/10.1016/0029-5493(87)90138-5.
- H. MURATA et al., “Natural Circulation Characteristics of a Marine Reactor in Rolling Motion,” Nucl. Eng. Des., 118, 2, 141 (1990); https://doi.org/https://doi.org/10.1016/0029-5493(90)90053-Z.
- H. MURATA et al., “Experimental Investigation of Natural Convection in a Core of a Marine Reactor in Rolling Motion,” J. Nucl. Sci. Technol., 37, 6, 509 (2000); https://doi.org/https://doi.org/10.1080/18811248.2000.9714924.
- H. MURATA et al., “Natural Circulation Characteristics of a Marine Reactor in Rolling Motion and Heat Transfer in the Core,” Nucl. Eng. Des., 215, 2, 69 (2002); https://doi.org/https://doi.org/10.1016/S0029-5493(02)00042-0.
- J. H. KIM et al., “Development of RETRAN03/MOV Code for Thermal Hydraulic Analysis of Nuclear Reactor Under Moving Conditions,” J. Korean Nucl. Soc., 28, 6, 542 (1996).
- C. L. TAN, H. ZHANG, and H. ZHAO, “Development of Ocean Condition Code Based on Relap5,” Nucl. Power Eng., 30, 6, 53 (2009).
- B. H. YAN and Y. LEI, “The Development and Validation of a Thermal Hydraulic Code in Rolling Motion,” Ann. Nucl. Energy, 38, 8, 1728 (2011); https://doi.org/https://doi.org/10.1016/j.anucene.2011.04.007.
- B. H. YAN and Y. LEI, “Theoretical Research for Natural Circulation Operation Characteristic of Ship Nuclear Machinery Under Ocean Conditions,” Ann. Nucl. Energy, 36, 6, 733 (2009); https://doi.org/https://doi.org/10.1016/j.anucene.2009.02.005.
- J. WU et al., “Research on Thermal Hydraulic Characteristics of Integrated Reactor in Natural Circulation Operation Under Ocean Motions,” Prog. Nucl. Energy, 126, 103399 (2020); https://doi.org/https://doi.org/10.1016/j.pnucene.2020.103399.
- L. H. HE et al., “Study on Natural Circulation Characteristics of an IPWR Under Inclined and Rolling Condition,” Nucl. Eng. Des., 317, 81 (2017); https://doi.org/https://doi.org/10.1016/j.nucengdes.2017.03.033.
- R. LI et al., “The Natural Circulation Flow Characteristic of the Core in Floating Nuclear Power Plant in Rolling Motion,” Ann. Nucl. Energy, 142, 107385 (2020); https://doi.org/https://doi.org/10.1016/j.anucene.2020.107385.
- R. LI et al., “The Simulation Study on Natural Circulation Operating Characteristics of FNPP in Inclined Condition,” Nucl. Eng. Technol., 51, 7, 1738 (2019); https://doi.org/https://doi.org/10.1016/j.net.2019.05.021.
- G. L. XIA et al., “Neutronic/Thermal-Hydraulic Coupling Analysis of Natural Circulation IPWR Under Ocean Conditions,” Ann. Nucl. Energy, 114, 4, 92 (2018); https://doi.org/https://doi.org/10.1016/j.anucene.2017.10.043.
- “RELAP5/MOD3 Code Manual: Code Structure, System Models, and Solution Methods. Volume 1,” NUREG/CR-5535-Vol.1, U.S. Nuclear Regulatory Commission (1995).
- D. LI, C. PENG, and R. HAO, “Simulation Investigation of Ocean Motion on Small Reactor Based on Modified System Code,” E3S Web Conf., 194, 01012 (2020); https://doi.org/https://doi.org/10.1051/e3sconf/202019401012
- I. Y. BAR-ITZHACK, “New Method for Extracting the Quaternion from a Rotation Matrix,” J. Guidance Control Dyn., 23, 6, 875 (2000); https://doi.org/https://doi.org/10.2514/2.4654.
- K. CHENG et al., “Development and Validation of Nuclear Reactor Thermal-Hydraulic System Analysis Code Under Ocean Conditions,” J. Harbin Eng. Univ., 38, 8, 1223 (2017).
- S. S. YIN et al., “Loss-of-Flow-Accidents (LOFA) Study for 100 Mw IPWR,” Proc. 22nd Int. Conf. Nuclear Engineering, Prague, Czech Republic, July 7–11, 2014.
- Y. ZHAO, M. J. PENG, and G. L. XIA, “Safety Evaluation of the Flashing-Driven Natural Circulation IPWR Against Loss-of-Feedwater Accident,” Ann. Nucl. Energy, 142, 7, 107408 (2020); https://doi.org/https://doi.org/10.1016/j.anucene.2020.107408.