참고문헌
- IAEA, Innovative Small and Medium Sized Reactors: Design Features, Safety Approaches and R&D Trends, IAEA-TECDOC-1451, International Atomic Energy Agency, 2005.
- IAEA, Status of Innovative Small and Medium Sized Reactor Designs 2005, IAEA-TECDOC-1485, International Atomic Energy Agency, 2006.
- IAEA, Status of Small and Medium Sized Reactor Designs, International Atomic Energy Agency, 2012.
- IAEA, Advances in Small Modular Reactor Technology Developments, International Atomic Energy Agency, 2014.
- Small Nuclear Power Reactor, World Nuclear Association [Internet]. 2016. Available from: http://www.world-nuclear.org/information-library/nuclearfuel-cycle/nuclear-power-reactors/small-nuclear-power-reactors.aspx.
- M.K. Rowinski, T.J. White, J. Zhao, Small and medium sized reactors (SMR): a review of technology, Renew. Sustain. Energy Rev. 44 (2015) 643-656. https://doi.org/10.1016/j.rser.2015.01.006
- H. Chang, S. He, J. Liu, Considerations for in-service inspection on pressure vessel of 200MW nuclear heating reactor, Nucl. Eng. Des. 202 (2000) 11-16. https://doi.org/10.1016/S0029-5493(00)00272-7
- Y. Shi, H. Chang, D. Dong, Some features of the nuclear heating reactor (NHR) design in China, Nucl. Eng. Des. 155 (1995) 597-602. https://doi.org/10.1016/0029-5493(95)00974-H
- K.K. Kim, W.J. Lee, S. Choi, H.R. Kim, J.J. Ha, SMART: the first licensed advanced integral Reactor, J. Energy Power Eng. 8 (2014) 94-102.
- J.N. Reyes, J. Groome, B.G. Woods, E. Young, K. Abel, Y. Yao, Y.J. Yoo, Testing of the multi-application small light water reactor (MASLWR) passive safety systems, Nucl. Eng. Des. 237 (2007) 1999-2005. https://doi.org/10.1016/j.nucengdes.2007.01.014
- Y.G. Lee, I.W. Park, G.C. Park, SBLOCA and LOFW experiments in a scaled down IET facility of REX-10 reactor, Nucl. Eng. Technol. 45 (2013) 347-360. https://doi.org/10.5516/NET.02.2013.024
- H.S. Park, B.Y. Min, Y.G. Jung, Y.C. Shin, Y.J. Ko, S.J. Yi, Design of the VISTA-ITL test facility for an integral type reactor of SMART and a post-test simulation of a SBLOCA test, Sci. Technol. Nucl. Ins. 2014 (2014) 1-14.
- H.S. Park, B.Y. Min, Y.C. Shin, S.J. Yi, Major results from safety-related integral effect tests with VISTA-ITL for the SMART design, in: Proceedings of ICAPP 12, 2012, June 24-28. Chicago, IL, USA.
- H.S. Park, B.Y. Min, Y.C. Shin, S.J. Yi, An integral effect test of complete loss of RCS flowrate for SMART with the VISTA-ITL, in: Transactions of the KNS Autumn Meeting, 2011, October 27-28. Gyeongju, Korea.
- B.Y. Min, H.S. Park, Y.C. Shin, S.J. Yi, Experimental verification on the integrity and performance of the passive residual heat removal system for a SMART design with VISTA-ITL, Ann. Nucl. Energy 71 (2014) 118-124. https://doi.org/10.1016/j.anucene.2014.03.001
- H.S. Park, S.J. Yi, C.H. Song, SMR accident simulation in experimental test loop, Nucl. Eng. Int. (2013) 12-15.
- A.N. Nahavandi, S. Castellana, E.N. Moradkhaniav, Scaling laws for modeling nuclear reactor systems, J. Nucl. Sci. Eng. 72 (1979) 75-83. https://doi.org/10.13182/NSE79-A19310
- M. Ishii, I. Kataoka, Similarity Analysis and Scaling Criteria for LWR's Under Single-Phase and Two-Phase Natural Circulation, NUREG/CR-3267, ANL-83-32, U.S. NRC, Washington, D.C, 1983.
- B.D. Chung, Y.I. Kim, H.C. Kim, K.H. Bae, Y.J. Jeong, Y.D. Hwang, C.H. Song, Development of a Phenomena Identification and Ranking Table (PIRT) of Thermal Hydraulic Phenomena for SMART, KAERI/TR-3780/2009, KAERI, 2009.
- W.P. Baek, C.H. Song, B.J. Yun, T.S. Kwon, S.K. Moon, S.J. Lee, KAERI integral effect test program and the ATLAS design, Nucl. Technol. 152 (2005) 183. https://doi.org/10.13182/NT05-A3669
- K.H. Kang, S.K. Moon, H.S. Park, S. Cho, K.Y. Choi, B.J. Yun, T.S. Kwon, S.J. Yi, C.K. Park, B.D. Kim, Y.S. Kim, C.H. Song, W.P. Baek, Detailed Description Report of ATLAS Facility and Instrumentation, KAERI/TR-4316/2011, KAERI, 2011.
- B.G. Jeon, Y.S. Cho, H. Bae, Y.S. Kim, S.U. Ryu, J.S. Suh, Code validation on a passive safety system test with the SMART-ITL facility, J. Nucl. Sci. Technol. 54 (2016) 322-329.
- A.C. Thadani, Attachment 1. Appendix K Decay Heat Standards-Research Information Letter 0202, NRC/RES-ML021720702, NRC, 2002.
피인용 문헌
- Comparison of Two Different Sized Small-Break LOCAs on the Passive Safety Injection Line Using SMART-ITL Data vol.206, pp.9, 2020, https://doi.org/10.1080/00295450.2020.1775450
- Reactor Coolant Pump Leakage Estimation of PWR Based on Broad Learning System vol.1939, pp.1, 2017, https://doi.org/10.1088/1742-6596/1939/1/012102
- Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL vol.382, pp.None, 2017, https://doi.org/10.1016/j.nucengdes.2021.111392
- Developing a robust and flexible smart tool to predict a full range Critical Heat Flux (CHF) in different LWRs by using deep learning Artificial Neural Networks (ANN) via parallel multi-processing vol.142, pp.None, 2017, https://doi.org/10.1016/j.pnucene.2021.103985