참고문헌
- H.R. Vega-Carrillo, I.R. Esparza-Garcia, A. Sanchez, Features of a subcritical nuclear reactor, Ann. Nucl. Energy 75 (2015) 101-106. https://doi.org/10.1016/j.anucene.2014.08.006
- N. Xoubi, Calculation of the power and absolute flux of a source driven subcritical assembly using Monte Carlo MCNP code, Ann. Nucl. Energy 97 (2016) 96-101. https://doi.org/10.1016/j.anucene.2016.07.009
- G. Klujber, J.L. Kloosterman, D. De Haas, Neutron noise measurements at the delphi subcritical assembly, in: Proc. PHYSOR 2012 Adv. React. Phys. - Link. Res. Ind. Educ, 2012, pp. 1-18.
- A. Talamo, et al., MCNPX, MONK, and ERANOS analyses of the YALINA Booster subcritical assembly, Nucl. Eng. Des. 241 (5) (2011) 1606-1615. https://doi.org/10.1016/j.nucengdes.2011.03.006
- N. Xoubi, Neutronic design study of accelerator driven system (ADS) for Jordan subcritical reactor as a neutron source for nuclear research, Appl. Radiat. Isot. 131 (2018) 71-76. https://doi.org/10.1016/j.apradiso.2017.11.011
- C.D. Bowman, et al., Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source, Nucl. Instrum. Methods Phys. Res. A 320 (1-2) (1992) 336-367. https://doi.org/10.1016/0168-9002(92)90795-6
- C. Rubbia, et al., Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier, 1995. CERN/AT/95-44.
- G. Perret, et al., Kinetic parameter measurements in the MINERVE reactor, IEEE Trans. Nucl. Sci. 64 (1) (2017) 724-734. https://doi.org/10.1109/TNS.2016.2637569
- A. Herrera-Martinez, Y. Kadi, G. Parks, M. Dahlfors, Transmutation of nuclear waste in accelerator-driven systems: fast spectrum, Ann. Nucl. Energy 34 (7) (2007) 564-578. https://doi.org/10.1016/j.anucene.2007.02.008
- Z. Chen, Y. Wu, B. Yuan, D. Pan, Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT), Ann. Nucl. Energy 75 (2015) 723-727. https://doi.org/10.1016/j.anucene.2014.09.002
- W. Kim, H.C. Lee, C.H. Pyeon, H.C. Shin, D. Lee, Monte Carlo analysis of the accelerator-driven system at kyoto university research reactor Institute, Nucl. Eng. Technol. 48 (2) (2016) 304-317. https://doi.org/10.1016/j.net.2015.12.001
- C. Rubbia, et al., Neutronic Analyses of the Trade Demonstration Facility, vol. 5639, 2004, pp. 103-123. October.
- X-5 Monte Carlo Team, "MCNP - a General Monte Carlo N-particle Transport Code, Version 5." LA-CP-03-0245, LANL, 2003.
- A. Dall'Osso, The influence of the neutron source spectrum on the infinite homogeneous reactor in subcritical condition, Ann. Nucl. Energy 77 (2015) 408-414. https://doi.org/10.1016/j.anucene.2014.12.006
- Z.I. Zafar, M.H. Kim, Embedded fission source approach to analyze external source effect in a subcritical reactor, Nucl. Eng. Des. 327 (2018) 238-247. April 2016. https://doi.org/10.1016/j.nucengdes.2017.11.039
- N. Xoubi, Neutrons and gamma-ray dose calculations in subcritical reactor facility using MCNP, Atoms 4 (3) (2016) 20. https://doi.org/10.3390/atoms4030020
- A. Gandini, On the multiplication factor and reactivity definitions for subcritical reactor systems, Ann. Nucl. Energy 29 (6) (Apr. 2002) 645-657. https://doi.org/10.1016/S0306-4549(01)00073-1
- K. Nishihara, T. Iwasaki, Y. Udagawa, A new static and dynamic one-point equation and analytic and numerical calculations for a subcritical system, J. Nucl. Sci. Technol. 40 (7) (2003) 481-492. https://doi.org/10.1080/18811248.2003.9715382
- H. Shahbunder, C.H. Pyeon, T. Misawa, J.Y. Lim, S. Shiroya, Subcritical multiplication factor and source efficiency in accelerator-driven system, Ann. Nucl. Energy 37 (9) (2010) 1214-1222. https://doi.org/10.1016/j.anucene.2010.04.010
- S. Zhou, et al., LAVENDER: a steady-state core analysis code for design studies of accelerator driven subcritical reactors, Nucl. Eng. Des. 278 (2014) 434-444. https://doi.org/10.1016/j.nucengdes.2014.07.027
- M. Turkmen, U. Colak, S. Ergun, Effect of burnup on the neutronic parameters of ITU TRIGA Mark II research reactor, Prog. Nucl. Energy 83 (2015) 26-34. https://doi.org/10.1016/j.pnucene.2015.02.012
- Z. Stancar, L. Barbot, C. Destouches, D. Fourmentel, J.F. Villard, L. Snoj, Computational validation of the fission rate distribution experimental benchmark at the JSI TRIGA Mark II research reactor using the Monte Carlo method, Ann. Nucl. Energy 112 (2018) 94-108. https://doi.org/10.1016/j.anucene.2017.09.039
- M.B. Chadwick, et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets 107 (12) (2006) 2931-3060. https://doi.org/10.1016/j.nds.2006.11.001
- R.K. Meulekamp, S.C. Van Der Marck, Calculating the effective delayed neutron fraction with Monte Carlo, Nucl. Sci. Eng. 152 (August) (2006) 142-148. https://doi.org/10.13182/NSE03-107
- B.C. Kiedrowski, et al., "MCNP5-1.60 Feature Enhancements & Manual Clarifications," No. LA-UR-10-06217, 2010.
- R. Henry, I. Tiselj, L. Snoj, Analysis of JSI TRIGA MARK II reactor physical parameters calculated with TRIPOLI and MCNP, Appl. Radiat. Isot. 97 (2015) 140-148. https://doi.org/10.1016/j.apradiso.2014.12.017
- International Atomic Energy Agency (IAEA) TRS 403, Compendium of Neutron Spectra and Detector Responses, 2001, p. 276, 403.
- N. Xu, et al., Elemental composition in sealed plutonium-beryllium neutron sources, Appl. Radiat. Isot. 95 (2015) 85-89. https://doi.org/10.1016/j.apradiso.2014.10.013
- L. Snoj, A. Kavcic, G. Zerovnik, M. Ravnik, Calculation of kinetic parameters for mixed TRIGA cores with Monte Carlo, Ann. Nucl. Energy 37 (2) (2010) 223-229. https://doi.org/10.1016/j.anucene.2009.10.020
- B. Verboomen, W. Haeck, P. Baeten, Monte Carlo calculation of the effective neutron generation time, Ann. Nucl. Energy 33 (10) (2006) 911-916. https://doi.org/10.1016/j.anucene.2006.05.001
- M. Hassanzadeh, S.A.H. Feghhi, H. Khalafi, Calculation of the neutron importance and weighted neutron generation time using MCNIC method in accelerator driven subcritical reactors, Nucl. Eng. Des. 262 (2013) 404-408. https://doi.org/10.1016/j.nucengdes.2013.04.037
- R.K. Meulekamp, S.C. Van Der Marck, Calculating the effective delayed neutron fraction with Monte Carlo, Nucl. Sci. Eng. 152 (2006) 142-148. https://doi.org/10.13182/NSE03-107
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