참고문헌
- J.P. Freidberg, A.C. Kadak, Fusion fission hybrids revisited, Nat. Phys. 5 (2009) 370-372. http://web.mit.edu/fusion-fission/HybridsPubli/nphys1288.pdf. https://doi.org/10.1038/nphys1288
- W.W. Engle Jr., ANISN, a One-dimensional Discrete Ordinates Transport Code with Anisotropic Scattering, 1970. ORNL-K-1693.
- L.M. Petrie, SCALE5-SCALE system driver, NUREG/CR-0200, revision 7, volume III, section M1, ORNL/NUREG/CSD-2/V3/r7, Oak ridge national laboratory and SCALE 6.2.2, a comprehensive modeling and simulation suite for nuclear safety analysis and design, SCALE website. http://scale.ornl.gov, 2004.
- S. Sahin, H. Yapici, S. Unalan, ERDEML_I, a Computer Program to Process ANISN Output Data, Gazi University, Faculty of Technology, Ankara, Turkey, 1991.
- S. Sahin, H. Yapici, Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel, Fusion Sci. Technol. 16 (3) (1989) 331-345. https://doi.org/10.13182/FST89-A29125
- S. Sahin, H. Yapici, Rejuvenation of light water reactor spent fuel in fusion blankets, Ann. Nucl. Energy 25 (16) (1998) 1317-1339. https://doi.org/10.1016/S0306-4549(98)00018-8
- S. Sahin, H. Yapici, Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation, Ann. Nucl. Energy 26 (1) (1999) 13-27. https://doi.org/10.1016/S0306-4549(98)00032-2
- S. Sahin, H. Yapici, M. Bayrak, Spent mixed oxide fuel rejuvenation in fusion breeders, Fusion Eng. Des. 47 (1) (1999) 9-23. https://doi.org/10.1016/S0920-3796(99)00066-6
- S. Sahin, H.M. Sahin, A. Sozen, M. Bayrak, Power flattening and minor actinide burning in a thorium fusion breeder, Energy Convers. Manag. 43 (6) (2002) 799-815. https://doi.org/10.1016/S0196-8904(01)00077-2
- S. Sahin, H.M. Sahin, K. Yildiz, Investigation of the effects of the resonance absorption in a fusion breeder blanket, Ann. Nucl. Energy 29 (14) (2002) 1641-1660. https://doi.org/10.1016/S0306-4549(02)00004-X
- M. Ubeyli, Neutronic performance of new coolants in a fusionefission (hybrid) reactor, Fusion Eng. Des. 70 (4) (2004) 319-328. https://doi.org/10.1016/j.fusengdes.2004.07.017
- H. Yapici, G. Genc, N. Demir, Numerical study on effects of fuel mixture fraction and Li-6 enrichment on neutronic parameters of a fusionefission hybrid reactor, J. Fusion Energy 23 (3) (2004) 191-205. https://doi.org/10.1007/s10894-005-5599-7
- S. Yalcin, M. Ubeyli, A. Acir, Neutronic analysis of a high power density hybrid reactor using innovative coolants, Sadhana 30 (4) (2005) 585-600. https://doi.org/10.1007/BF02703281
- A. Acir, M. Ubeyli, Burning of reactor grade plutonium mixed with thorium in a hybrid reactor, J. Fusion Energy 26 (3) (2007) 293-298. https://doi.org/10.1007/s10894-007-9078-1
- S. Sahin, H.M. Sahin, A. Acir, Utilization of TRISO fuel with reactor grade plutonium in CANDU reactors, Nucl. Eng. Des. 240 (8) (2010) 2066-2074. https://doi.org/10.1016/j.nucengdes.2010.04.008
- S. Sahin, H.M. Sahin, A. Acir, LIFE hybrid reactor as reactor grade plutonium burner, Energy Convers. Manag. 63 (2012) 44-50. https://doi.org/10.1016/j.enconman.2011.12.031
- S. Sahin, H.M. Sahin, A. Acir, Criticality and burn up evolutions of the fixed bed nuclear reactor with alternative fuels, Energy Convers. Manag. 51 (9) (2010) 1781-1787. https://doi.org/10.1016/j.enconman.2009.12.044
- S. Sahin, H.M. Sahin, M. Alkan, K. Yildiz, An assessment of thorium and spent LWR-fuel utilization potential in CANDU reactors, Energy Convers. Manag. 45 (7-8) (2004) 1067-1085. https://doi.org/10.1016/j.enconman.2003.08.002
- S. Sahin, H.M. Sahin, A. Acir, T.A. Al-Kusayer, "Criticality investigations for the fixed bed nuclear reactor using thorium fuel mixed with plutonium or minor actinides, Ann. Nucl. Energy 36 (8) (2009) 1032-1038. https://doi.org/10.1016/j.anucene.2009.06.003
- S. Sahin, K. Yildiz, H.M. Sahin, N. Sahin, A. Acir, Increased fuel burn up in a CANDU thorium reactor using weapon grade plutonium, Nucl. Eng. Des. 236 (17) (2006) 1778-1788. https://doi.org/10.1016/j.nucengdes.2006.01.014
- S. Sahin, K. Yildiz, H.M. Sahin, A. Acir, Investigation of CANDU reactors as a thorium burner, Energy Convers. Manag. 47 (13-14) (2006) 1661-1675. https://doi.org/10.1016/j.enconman.2005.10.013
- H.M. Sahin, Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor, Ann. Nucl. Energy 34 (11) (2007) 861-870. https://doi.org/10.1016/j.anucene.2007.04.011
- H.M. Sahin, A. Acir, T. Altinok, S. Yalcin, Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor, Energy Convers. Manag. 49 (7) (2008) 1960-1965. https://doi.org/10.1016/j.enconman.2007.09.028
- H.M. Sahin, G. Tunc, N. Sahin, Investigation of tritium breeding ratio using different coolant material in a fusionefission hybrid reactor, Int. J. Hydrogen Energy 41 (17) (2016) 7069-7075. https://doi.org/10.1016/j.ijhydene.2015.11.174
- M. Kotschenreuther, P.M. Valanju, S.M. Mahajan, E.A. Schneider, Fusionefission transmutation schemedefficient destruction of nuclear waste, Fusion Eng. Des. 84 (1) (2009) 83-88. https://doi.org/10.1016/j.fusengdes.2008.11.019
- M. Matsunaka, M. Ohta, K. Kondo, H. Miyamaru, I. Murata, Speed-up of crosssection collapsing with weight-window for subcritical burnup calculation, Fusion Eng. Des. 84 (7) (2009) 1281-1284. https://doi.org/10.1016/j.fusengdes.2008.12.020
- M. Matsunaka, M. Ohta, H. Miyamaru, I. Murata, Advanced burnup calculation code system in a subcritical state with continuous-energy Monte Carlo code for fusion-fission hybrid reactor, J. Nucl. Sci. Technol. 46 (8) (2009) 776-786. https://doi.org/10.1080/18811248.2007.9711585
- X.B. Ma, Y.X. Chen, Y. Wang, P.Z. Zhang, B. Cao, D.G. Lu, H.P. Cheng, "Neutronic calculations of a thorium-based fusionefission hybrid reactor blanket, Fusion Eng. Des. 85 (10) (2010) 2227-2231. https://doi.org/10.1016/j.fusengdes.2010.08.044
-
Z. Zhou, Y. Yang, H. Xu, <
https://doi.org/10.1088/0029-5515/51/10/103011 - Y. Zheng, T. Zu, H. Wu, L. Cao, C. Yang, "The neutronics studies of a fusion fission hybrid reactor using pressure tube blankets, Fusion Eng. Des. 87 (9) (2012) 1589-1596. https://doi.org/10.1016/j.fusengdes.2012.05.001
- T. Zu, H. Wu, Y. Zheng, L. Cao, C. Yang, "NAPTH: neutronics analysis code system for the fusionefission hybrid reactor with pressure tube type blanket, Fusion Eng. Des. 88 (3) (2013) 170-176. https://doi.org/10.1016/j.fusengdes.2013.02.014
- R. Holly, I. David, H.R. Trellue, User's Manual, Version 2.0 for MONTEBURNS, Version 5B, Los Alamos National Laboratory, 1999.
- M.T. Siddique, M.H. Kim, << Conceptual design study of Hyb-WT as fusionefission hybrid reactor for waste transmutation, Ann. Nucl. Energy 65 (2014) 299-306. https://doi.org/10.1016/j.anucene.2013.11.020
- S.C. Xiao, J. Zhao, Z. Zhou, Y. Yang, "Neutronic study of a molten salt cooled natural thoriumeuranium fuelled fusionefission hybrid energy system, J. Fusion Energy 34 (2) (2015) 352-360. https://doi.org/10.1007/s10894-014-9808-0
- F. Carminati, C. Roche, J.A. Rubio, C. Rubbia, J.P.C. Revol, R. Klapisch, An Energy Amplifier for Cleaner and Inexhaustible Nuclear Energy Production Driven by a Particle Beam Accelerator, 1993 (No. CERN-AT-93-47-ET). P00019698.
- C. Rubbia, J.A. Rubio, S. Buono, F. Carminati, N. Fietier, J. Galvez, C. Geles, Y. Kadi, R. Klapisch, P. Mandrillon, J.P. Revol, Ch Roche, Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier, 1995 (No. CERN-AT-95-44-ET).
- C. Rubbia, S. Buono, Y. Kadi, J.A. Rubio, Fast Neutron Incineration in the Energy Amplifier as Alternative to Geologic Storage: the Case of Spain (No. CERN-lhc-97-001-eet), 1997.
- S.B. Degweker, P.V. Bhagwat, S. Krishnagopal, A. Sinha, "Physics and technology for development of accelerator driven systems in India, Prog. Nucl. Energy 101 (2017) 53-81. https://doi.org/10.1016/j.pnucene.2017.04.001
- H.A. Abderrahim, P. Baeten, D. De Bruyn, R. Fernandez, "MYRRHAeA multipurpose fast spectrum research reactor, Energy Convers. Manag. 63 (2012) 4-10. https://doi.org/10.1016/j.enconman.2012.02.025
- R. Barlow, J. Burlison, T. Edwards, A. Healy, A. Masterson, H.A. Abderrahim, G. Van den Eynde, Studies of MYRRHA using thorium fuel, Int. J. Hydrogen Energy 41 (17) (2016) 7175-7180. https://doi.org/10.1016/j.ijhydene.2016.02.141
- A. Stankovskiy, H. Iwamoto, Y. Celik, G. Van den Eynde, High-energy nuclear data uncertainties propagated to MYRRHA safety parameters, Ann. Nucl. Energy 120 (2018) 207-218. https://doi.org/10.1016/j.anucene.2018.05.041
- X-5 Monte Carlo Team, MCNP5 - a General Monte Carlo, N-particle Transport Code, Version 5, LA-CP-03-0245, Los Alamos National Laboratory, 2005.
- Y. Wu, Z. Chen, L. Hu, et al., Identification of safety gaps for fusion demonstration reactors, Nature Energy 1 (2016) 16154. https://doi.org/10.1038/nenergy.2016.154
- Y. Wu, Y. Bai, Y. Song, et al., Development strategy and conceptual design of China lead-based research reactor, Ann. Nucl. Energy 87 (2016) 511-516. https://doi.org/10.1016/j.anucene.2015.08.015
- Y. Wu, Design and R&D progress of China lead-based reactor for ADS research facility, Engineering 2 (1) (2016) 124-131. https://doi.org/10.1016/J.ENG.2016.01.023
- Y. Wu, Development of high intensity DeT fusion neutron generator HINEG,, International Journal of Energy Research 42 (1) (2018) 68-72. https://doi.org/10.1002/er.3572
- G. Tunc, The Neutronic Analysis of the Performances of Thorium and Various Nuclear Fuels in a Fusion-fission Reactor System (PhD thesis in Turkish), Gazi University, Ankara, Turkey, 2017.
- C.V. Parks, SCALE-4.3: Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation for Workstations and Personal Computers, 1995. CCC-545.
- W.E. Shoupp, J.E. Hill, Thresholds for fast neutron fission in thorium and uranium, Phys. Rev. 75 (1949) 785. https://doi.org/10.1103/PhysRev.75.785
- J.R. Lamarsh, A.J. Baratta, Introduction to Nuclear Engineering, third ed., Pearson, 2001.
- S. Sahin, J. Ligou, The effect of the spontaneous fission of 240Pu on the energy release in a nuclear explosive, Nucl. Technol. 50 (1980) 88-94. https://doi.org/10.13182/NT80-A17072
피인용 문헌
- Large‐scale energy production with thorium in a typical heavy‐water reactor using high‐grade plutonium as driver fuel vol.43, pp.2, 2019, https://doi.org/10.1002/er.4335
- Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors vol.44, pp.7, 2020, https://doi.org/10.1002/er.5330