This study presents the possibility of the power flattening in the ARIES-RS breeder reactor using mixed (Th,U)C or (Th,U)N fuels. Two different types of mixing, namely, homogeneous mixing (HM) and linear mixing (LM) were used to investigate the uniformity of fission power distribution through the fuel zone. In HM, fraction of uranium content were kept constant in all rows of the fuel zone whereas, in LM the fraction of the uranium were linearly increased from the first to last fuel row in the fuel zone. Neutron transport calculations were performed with the aid of the SCALE4.3 system by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and a S8–P3 approximation. Flat fission power distribution was maintained successfully for the blanket using linearly mixed fuels. However, the fission density profile was not uniform in the blanket with homogeneously mixed fuels. It decreased exponentially form the 1st to 10th fuel row.
Similar content being viewed by others
References
W. J. Hogan and E. Bertel, Introduction: Inertial Fusion Energy Fundamentals, Energy from Inertial Fusion, Editors; W. J. Hogan, J. Coutant, S. Nakai, V.B. Rozanov, and G. Velarde, IAEA, Vienna (1995)
D. H. Berwald, et al., Fission Suppressed Hybrid Reactor Fusion Breeder, Lawrence Livermore National Laboratory, UCID-19327 (1982)
E. Greenspan, Fusion–Fission Hybrid Reactors, Advances in Science and Technology, J. LEWINS and M. BECKER, Eds., Plenum Press, 16, 289 (1984)
R. W. Moir, The Fusion Breeder, submitted to the National Science Foundation Policy Workshop, Washington DC, March 4–5, Lawrence Livermore Laboratory, CA, UCRL-87290 (1982).
M. H. Raghep, et al., Nuclear Performance of Molten Salt Fusion-Fission Symbiotic System for Catalyzed D–D and D–T Reactors, ORNL-TM-6560, Oak Ridge National Laboratory (1979)
S. Şahin T. A. Al-Kusayer M. A. Raoof (1986) Fusion Technology 10 84
S. Şahin H. Yapııcıı (1989) Fusion Technology 16 331
H. Yapııcıı N. Şahin M. Bayrak (2000) Energy Conversion and Management 41 IssueID435 41–435
H. Yapııcıı M. Übeyli Ş. Yalçıın (2002) Annals of Nuclear Energy 29 1871 Occurrence Handle10.1016/S0306-4549(02)00016-6
H. Yapıcı O. İpek M. Übeyli (2003) Energy Conversion and Management 44 573
H. Yapı ıcı ı (2003) Fusion Engineering and Design 65 599
M. S. Tillack (1989) Fusion Engineering and Design 41 491 Occurrence Handle10.1016/S0920-3796(97)00161-0
F. Najmabadi (1998) Fusion Engineering and Design 41 365 Occurrence Handle10.1016/S0920-3796(97)00153-1 Occurrence Handle1:CAS:528:DyaK1cXls1eqsLY%3D
R. W. Conn F. Najmabadi M. S. Tillack (1998) Fusion Engineering and Design 41 337 Occurrence Handle10.1016/S0920-3796(97)00152-X Occurrence Handle1:CAS:528:DyaK1cXls1eqsLs%3D
L. A. El-Guebaly (1997) Fusion Engineering and Design 38 139 Occurrence Handle10.1016/S0920-3796(97)00114-2 Occurrence Handle1:CAS:528:DyaK1cXhtVCjtw%3D%3D
D. Steiner L. El-Guebaly S. Herring H. Khater E. Mogahed et al. (1997) Fusion Engineering and Design 38 189 Occurrence Handle10.1016/S0920-3796(97)00116-6 Occurrence Handle1:CAS:528:DyaK1cXhtVCjtQ%3D%3D
S. Şahin S Yalçı ın H. M. Şahin M. Übeyli (2003) Annals of Nuclear Energy 30 IssueID2 245 Occurrence Handle10.1016/S0306-4549(02)00049-X
M. Übeyli (2004) Journal of Fusion Energy 23 IssueID1 41 Occurrence Handle10.1007/s10894-004-1870-6
K. Erickson N. Y. McCormick G. L. Woodruff (1981) Nuclear Technology 1 553
E. Greenspan A. Misulovin D. Gilal (1983) Nuclear Technology 3 485 Occurrence Handle1:CAS:528:DyaL3sXitVGrtbk%3D
S. Şahin (1989) Kerntechnik 53 285
S. Şahin (1999) Nuclear Technology 92 93
H. Yapı ıcı ı M. Übeyli (2003) Annals of Nuclear Energy 30 159
H. Yapı ıcı ı (2003) Fusion Engineering and Design 65 89
W. C. Jordan and S. M. Bowman, “Scale Cross-Section Libraries”, NUREG/CR-0200, Revision 5, 3, section M4, ORNL/NUREG/CSD-2/V3/R5, Oak Ridge National Laboratory (1997)
N. M. Greene and L. M. Petrie, “XSDRNPM, A One-Dimensional Discrete-Ordinates Code For Transport Analysis”, NUREG/CR-0200, Revision 5, 2, Section F3, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory (1997)
S. Şahin, Radiation Shielding Calculations For Fast Reactors (in Turkish), Gazi University, Publication # 169, Faculty of Science and Literature, Publication number 22, Ankara, Turkey (1991)
H. Yapı ıcı ı (2001) XSCALC for Interfacing Output of XSDRN to Calculate Integral Neutronic Data Erciyes University Kayseri, Turkey
N. M. Greene, “BONAMI, Resonance Self-Shielding by the Bondarenko Method”, NUREG/CR-0200, Revision 5, 2, section F1, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory (1997)
N. M. Greene, L. M. Petrie, and R. M. Westfall, “NITAWL-II, Scale System Module For Performing Resonance Shielding and Working Library Production”, NUREG/CR-0200, Revision 5, 2, Section F2, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory (1997)
N. F. Landers and L. M. Petrie, “CSAS, Control Module for Enhanced Criticality Safety Analysis Sequences”, NUREG/CR-0200, Revision 5, 1, Section C4, ORNL/NUREG/CSD-2/V1/R5, Oak Ridge National Laboratory (1997)
S. Şahin H. Yapı ıcı ı (1999) Annals of Nuclear Energy 26 13 Occurrence Handle10.1016/S0306-4549(98)00032-2
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Übeyli, M. Power Flattening in ARIES-RS Fusion Breeder Reactor Using Mixed Fuels. J Fusion Energ 23, 263–269 (2004). https://doi.org/10.1007/s10894-005-5618-8
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10894-005-5618-8