과제정보
This work was supported by the Nuclear Research & Development Program of the National Research Foundation with a grant funded by the Korea Ministry of Science and ICT (No. 2012M2A8A2025633) and the National Council of Science & Technology (NST) grant by the Korea government (MSIT) (No. CAP-20-03-KAERI).
참고문헌
- Philippe Dufour, Sodium Fast Reactor, 3rd GIF Symposium 2015/ICONE23 Conference, 2015. Japan.
- Giorgio Locatelli, Mauro Mancini, Nicola Todeschini, Generation IV nuclear reactors: current status and future prospects, Energy Pol. 61 (2013) 1053-1520.
- Iaea, Advances in Small Modular Reactor Technology Developments, A Supplement to, IAEA Advanced Reactors Information System (ARIS), 2018.
- ASME Boiler and Pressure Vessel Code, ASME, 2017. Section III, Division 5.
- RCC-MRx, Design and Construction Rules for Mechanical Components of Nuclear Installations, High Temperature, Research and Fusion Reactors, AFCEN, 2018.
- R5, Assessment Procedure for the High Temperature Response of Structures, British Energy Generation Ltd., 2012.
- JSME, Code for Nuclear Power Generation Facilities, Rules on Design and Construction for Nuclear Power Plants, Section II Fast Reactor Standard, JSME, 2012.
- J.W. Yoo, J.W. Chang, J.Y. Lim, J.S. Cheon, T.H. Lee, S.K. Kim, K.L. Lee, H.K. Joo, Overall system description and safety characteristics of prototype gen IV sodium cooled fast reactor in Korea, Nuclear Engineering and Technology 48 (2016) 1059-1070. https://doi.org/10.1016/j.net.2016.08.004
- N.H. Kim, S.K. Kim, High Temperature Design and Evaluation of Forced Draft Sodium-To-Air Heat Exchanger in PGSFR, International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17) Programme and Papers, International Atomic Energy Agency (IAEA), 2017.
- G.H. Koo, J.H. Lee, Development of an ASME-NH program for nuclear component design at elevated temperatures, Int. J. Pres. Ves. Pip. 85 (2008) 385-393. https://doi.org/10.1016/j.ijpvp.2007.11.012
- D.H. Cho, S.H. Bum, J.B. Choi, N.S. Huh, Y.H. Choi, Development of Web-Based Design Compatibility Assessment Program for High Temperature Reactor, vol. 9, Transaction of the Korean Society of Pressure Vessels and Piping, 2013, pp. 48-55. https://doi.org/10.20466/KPVP.2013.9.1.048
- M.J. Swindeman, R.I. Jetter, T.-L. Sham, Report on the FY17 Development of Computer Program for ASME Section III, Division 5, Subsection HB, Subpart B Rules, Argonne National Laboratory, 2017. ANL-ART-91.
- J. Bree, Elastic-plastic behaviour of thin tubes subjected to internal pressure and intermittent high-heat fluxes with application to fast-nuclear-reactor fuel elements, J. Strain Anal. 2 (1967) 226-238. https://doi.org/10.1243/03093247V023226
- ANSYS Mechanical APDL Manual, Theory Reference (Chapter 15.7: Spectrum Analysis), Rev. 15.0, ANSYS Inc.
- ASME Boiler and Pressure Vessel Code, Section II, Part D, ASME, 2017.