참고문헌
- G. Haratyk, C. Lecomte, F.X. Briffod, Flexblue(R): a subsea and transportable small modular power plant, in: Proceedings of ICAPP, 2014. Charlotte, USA.
- J. Buongiorno, J. Jurewicz, M. Golay, N. Todreas, The offshore floating nuclear plant concept, Nucl. Technol. 194 (2016) 1-14. https://doi.org/10.13182/NT15-49
- K. Shirvan, G. Haratyk, R. Ballinger, J. Buongiorno, C. Forsberg, M. Kazimi, N. Todreas, Advanced offshore seabed reactors, in: Proceedings of ICAPP, 2015. Nice, France.
- M. Galvin, N. Todreas, L. Conway, Maintenance cycle extension in the IRIS advanced light water reactor, Nucl. Technol. 143 (2003) 270-280. https://doi.org/10.13182/NT03-A3416
- N. Yoshida, M. Kawakami, K. Hiraiwa, H. Heki, Study on long life core with uranium fuel for LSBWR, in: Proceedings of PHYSOR, 2002. Seoul, Korea.
- Y.C. Ko, M.S. Kazimi, Conceptual design of an annular-fueled superheat boiling water reactor, MIT-ANP-TR-130, MIT, Cambridge (MA), USA, 2010.
- G. Toshinsky, V. Petrochenko, Modular lead-bismuth fast reactors in nuclear power, Sustainability 4 (2012) 2293-2316. https://doi.org/10.3390/su4092293
- K. Shirvan, R. Ballinger, J. Buongiorno, C. Forsberg, M. Kazimi, N. Todreas, Advanced offshore seabed reactors, MIT-ANPTR-155, MIT, Cambridge (MA), 2014.
- International Atomic Energy Agency (IAEA), Status of small and medium sized reactor designs, September 2011.
- J. Buongiorno, J.W. Sterbentz, P.E. MacDonald, Study of solid moderators for the thermal-spectrum supercritical watercooled reactor, Nucl. Technol. 153 (2006) 282-303. https://doi.org/10.13182/NT06-A3708
- E.D. Greaves, K. Furukawa, L. Sajo-Bohus, H. Barros, The case for the thorium molten salt reactor, Proc. Latin Am. Symp. Nucl. Phys. Appl. 1423 (2012) 453-460.
- C. Forsberg, D. Curtis, J. Stempien, R. MacDonald, P. Peterson, Fluoride-salt-cooled high-temperature reactor (FHR) commercial basis and commercialization strategy, MIT-ANPTR-153, MIT, Cambridge (MA), USA, 2014.
- E.A. Hoffman, W.S. Yang, R.N. Hill, Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios, ANL-AFCI-177, ANL, Chicago, USA, 2006.
- K. Kunitomi, S. Katanishi, S. Takada, T. Takizuka, X. Yan, Japan's future HTR-the GTHTR300, Nucl. Eng. Design 233 (2004) 309-327. https://doi.org/10.1016/j.nucengdes.2004.08.026
- P. Anzieu, R. Stainsby, K. Mikityuk, Gas-cooled fast reactor (GFR): overview and perspectives, in: Proceedings of the GIF Symposium, 2009. Paris, France.
- P. Hejzlar, N.E. Todreas, E. Shwageraus, A. Nikiforova, R. Petroski, M.J. Driscoll, Cross-comparison of fast reactor concepts with various coolants, Nucl. Eng. Design 239 (2009) 2672-2691. https://doi.org/10.1016/j.nucengdes.2009.07.007
- M.A. Erighin, A 48 month extended fuel cycle for the B&W mPowerTM small modular nuclear reactor, in: Proceedings of PHYSOR, 2012. Knoxville, USA.
- K. Shirvan, P. Hejzlar, M.S. Kazimi, The design of a compact integral medium size PWR, Nucl. Eng. Design 243 (2012) 393-403. https://doi.org/10.1016/j.nucengdes.2011.11.023
- J.M. Cronje, J.J. Van Wyk, M.J. Memmott, Overview of the Westinghouse small modular reactor building layout, in: Proceedings of ICAPP 2012, June 24-28, 2012. Chicago, USA.
- M.J. Memmott, A. Manera, The use of a flashing drum to generate steamin the integral, inherently safe (I2S) light water reactor, in: Proceedings of ICAPP 2014, 2014. Charlotte, USA.
- HEATRICTM [Internet]. [cited 2008 Dec]. Available from: http://www.heatric.com.
- G. Haratyk, K. Shirvan, M. Kazimi, Compact steam generator for nuclear application, Proceedings of NURETH16, 2015. Chicago, USA.
- Aspentech, ASPENONE V8 [Internet]. 2014. Available from: http://www.aspentech.com/products/.
- S. Dewson, C. Grady, HEATRIC Workshop at MIT, Cambridge, MA, USA, 2003.
- Measuring Worth [Internet]. 2010. Available from: http://www.measuringworth.com/uscompare/.
- KAERI, Status report 77 d System-Integrated Modular Advanced Reactor (SMART) [Internet]. Available from:, 2011 https://aris.iaea.org/sites/..%5CPDF%5CSMART.pdf.
- H. Bae, D.E. Kim, S.U. Ryu, J.-S. Suh, An SBLOCA test of safety injection line break with the SMART-ITL facility and its MARSKScode simulation, in: Proceedings of ICAPP, 2014 paper 14140.
- F. Incropera, Fundamentals of Heat and Mass Transfer, fifth ed., John Wiley and Sons, New York, USA, 2002.
- D. Feng, P. Hejzlar, M.S. Kazimi, Thermalehydraulic design of high-power-density annular fuel in PWRs, Nucl. Technol. 160 (2007) 16-44. https://doi.org/10.13182/NT07-A3882
- Y.S. Yang, D.H. Kim, J.G. Bang, H.K. Kim, T.H. Chun, K.S. Kim, K.W. Song, C.G. Seo, H.T. Chae, Irradiation test of dual-cooled annular fuel pellets, in: Proceedings of WRFPM/Top Fuel, 2009. Paris, France.
- B.A. Pint, K.A. Terrani, M.P. Brady, T. Cheng, J.R. Keiser, High temperature oxidation of fuel cladding candidate materials in steamehydrogen environments, J. Nucl. Mater. 440 (2013) 420-427. https://doi.org/10.1016/j.jnucmat.2013.05.047
- K. Shirvan, M. Kazimi, Superheated water small modular underwater reactor concept, J. Nucl. Eng. Technol. 48 (2016) 1338-1348. https://doi.org/10.1016/j.net.2016.06.003
- M. Short, R.G. Ballinger, H.E. H€anninen, Corrosion resistance of alloys F91 and Fee12Cre2Si in leadebismuth eutectic up to 715C, J. Nucl. Mater. 434 (2013) 259-281. https://doi.org/10.1016/j.jnucmat.2012.11.010
- P. Kasten, R. Adama, R. Carlsmith, R. Chapman, E. Epler, E. Gift, F. Harrington,M.Myers, R. Olson, J. Roberts, R. Solmon, J.Sanders,R. Stone, D.Vondy, C.Walker,T.Washburn, L.Yeatts, F. Zapp, An evaluation of heavy-water-moderated organiccooled reactors, ORNL-3921, ORNL, Knoxville, USA, 1967.
- M.T. Simnad, The U-ZrHx alloy: its properties and use in TRIGA fuel, Nucl. Eng. Design 64 (1981) 403-422. https://doi.org/10.1016/0029-5493(81)90135-7
- P. Macdonald, J. Buongiorno, C. Davis, K. Weaver, R. Latanision, B. Mitton, G. Was, M. Carelli, D. Paramonov, L. Conway, Feasibility study of supercritical light water cooled fast reactors for actinide burning and electric power production, INEEL/EXT-02-00925, INL, Idaho Falls, USA, 2002.
- K. Shirvan, E. Forrest, Design of an organic simplified nuclear reactor, J. Nucl. Eng. Technol. 48 (2016) 893-905. https://doi.org/10.1016/j.net.2016.02.019
-
S.A. Wrights, R.F. Radel, T.M. Conboy, G.E. Rochau, Modeling and experimental results for condensing supercritical
$CO_2$ power cycles, SAND2010-8840, Sandia National Lab, Albuquerque, USA, 2011. - Siemens, ''Industrial Steam Turbines: The comprehensive product range from 2 to 250 megawatts [Internet]. [cited 2013]. Available from: http://www.energy.siemens.com/us/pool/hq/power-generation/steam-turbines/Industrial_Steam_Turbines_en.pdf.
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- Energy and exergy analyses of a hybrid small modular reactor and wind turbine system for trigeneration vol.7, pp.6, 2016, https://doi.org/10.1002/ese3.327
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