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Neutronic analysis of a high power density hybrid reactor using innovative coolants

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Abstract

In this study, neutronic investigation of a deuterium-tritium (DT) driven hybrid reactor using ceramic uranium fuels, namely UC, UO2 or UN under a high neutron wall load (NWL) of 10MW/m2 at the first wall is conducted over a period of 24 months for fissile fuel breeding for light water reactors (LWRs). New substances, namely, Flinabe or Li20Sn80 are used as coolants in the fuel zone to facilitate heat transfer out of the blanket. Natural lithium is also utilized for comparison to these two innovative coolants. Neutron transport calculations are performed on a simple experimental hybrid blanket with cylindrical geometry with the help of the SCALE 4.3 System by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and an S8-P3 approximation. The investigated blanket using Flinabe or Li20Sn80 shows better fissile fuel breeding and fuel enrichment characteristics compared to that with natural lithium which shows that these two innovative coolants can be used in hybrid reactors for higher fissile fuel breeding performance. Furthermore, using a high NWL of 10MW/m2 at the first wall of the investigated blanket can decrease the time for fuel rods to reach the level for charging in LWRs.

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References

  • Abdou M A 1999On the exploration of innovative concepts for fusion chamber technology. APEX Interim Report (Overview), UCLA-ENG-99-206, UCLA-FNT-107, University of California, Los Angeles, CA

    Google Scholar 

  • Berwald D Het al 1982 Fission Suppressed Hybrid Reactor Fusion Breeder, Lawrence Livermore National Laboratory, UCID-19327

  • Bettis E S, Robertson R C 1970 Design and performance features of a single-fluid molten salt breeder reactor.Nucl. Appl. Tech. 8: 190–207

    Google Scholar 

  • Greene N M 1997 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, Oak Ridge, TN

    Google Scholar 

  • Greene N M, Petrie L M 1997 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

  • Greene N M, Petrie L M, Westfall RM 1997 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

  • Grimes W R, Cantor S 1972 Molten salt as blanket fluids in controlled fusion reactors. InThe chemistry of fusion technology (New York: Plenum)

    Google Scholar 

  • Greenspan E 1984 Fusion-fission hybrid reactors.Advances in science and technology (eds) J Lewins, M Becker (New York: Plenum) 16: 289

    Google Scholar 

  • Jaeger R G, Blizard E P, Chilton A B, Grotenhuis M, Hönig A Th, Jaeger A, Eisenlohr H H 1968 Shielding fundamentals and methods.Engineering compendium on radiation shielding, I (Berlin: Springer-Verlag)

    Google Scholar 

  • Jordan W C, Bowman S M 1997 Scale cross-section libraries. NUREG/CR-0200, Revision 5, 3, section M4, ORNL/NUREG/CSD-2/V3/R5, Oak Ridge National Laboratory, Oak Ridge, TN

    Google Scholar 

  • Landers N F, Petrie L M 1997 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

  • Lee J Det al 1982 Feasibility Study of a Fission-Suppressed Tandem-Mirror Hybrid Reactor Fusion Breeder, Lawrence Livermore National Laboratory, CA, UCID-19327

    Google Scholar 

  • Malinauskas A P, Richardson D M 1974 The solubilities of hydrogen, deuterium and helium in molten LiF-BeF2.Ind. Eng. Chem. Fundam. 13: 242–252

    Article  Google Scholar 

  • Meyer W, Loyalka S K, Nelson W E, Williams R W 1977 The homemade nuclear bomb syndrome.Nuclear Safety 18:427

    Google Scholar 

  • Moir R W 1982 The fusion breeder. Submitted to the National Science Foundation Policy Workshop, Washington DC, March 4–5, Lawrence Livermore Laboratory, CA, UCRL-87290

  • Moriyama H, Sagara A, Tanaka S, Moir R W, Sze D K 1998 Molten salts in fusion nuclear technology.Fusion Eng. Design 39–40: 627–637

    Article  Google Scholar 

  • Moriyama H, Tanaka S, Sze D K, Reimann J, Terlain A 1995 Tritium recovery from liquid metals.Fusion Eng. Design 28: 226–239

    Google Scholar 

  • Raghep M Het al 1979 Nuclear performance of molten salt fusion-fission symbiotic system for catalyzed D-D and D-T reactors. ORNL-TM-6560, Oak Ridge National Laboratory, Oak Ridge, TN

    Google Scholar 

  • Şahin S 1980 Reply to the remarks on the plutonium-240 induced preignition problem in a nuclear device,Nucl. Technol. 54: 431–432

    Google Scholar 

  • Şahin S 1982 Addendum to “Reply to remarks on the plutonium-240 induced pre-ignition problem in a nuclear device.”Nucl. Technol. 58: 354

    Google Scholar 

  • Şahin S 1990 Power flattening in a catalysed deuterium-deuterium fusion-driven hybrid blanket using nuclear waste actinides.Nucl. Technol. 92, 93–105

    Google Scholar 

  • Şahin S 1991Radiation shielding calculations for fast reactors. Gazi University, Publication # 169, Faculty of Science and Literature, Publication number 22, Ankara, Turkey (in Turkish)

  • Şahin S, Al-Kusayer T 1985 Conceptual design studies of a cylindrical experimental ThO2 blanket with (D,D) driver.Kerntechnik 47: 259–266

    Google Scholar 

  • Şahin S, Ligou J 1980 The effect of the spontaneous fission of plutonium-240 on the energy release in a nuclear explosive.Nucl. Technol. 50: 88–94

    Google Scholar 

  • Şahin S, Übeyli M 2004a Modified apex reactor as a fusion breeder.Energy Conver. Manage. 45: 1497–1512

    Article  Google Scholar 

  • Şahin S, Übeyli M 2004b LWR Spent fuel transmutation in a high power density fusion reactor.Ann. Nucl. Energy 31: 871–890

    Article  Google Scholar 

  • Şahin S, YapiciH 1989 Investigation of the neutronic potential of moderated and fast (D,T) hybrid blankets for rejuvenation of CANDU spent fuel.Fusion Technol. 16: 331–345

    Google Scholar 

  • Şahin S, YapiciH 1998 Rejuvenation of LWR fuel in fusion blankets.Ann. Nucl. Energy 25:1317–1339

    Article  Google Scholar 

  • Şahin S, YapiciH 1999a Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation.Ann. Nucl. Energy 26: 13–27

    Article  Google Scholar 

  • Şahin S, Al-Kusayer T A, Raoof M A 1986 Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver.Fusion Technol. 10: 84–99

    Google Scholar 

  • Şahin S, YapiciH, Baltacioglu E, Al-Kusayer T A 1991 a A hybrid reactor design concept driven by cold (D,T) fusion neutrons and fueled with metallic thorium.Int. J. Energy-Environ.-Econ. 1: 167–173

    Google Scholar 

  • Şahin S, Baltacioglu E, YapiciH 1991b Potential of a catalysed fusion-driven hybrid reactor for the regeneration of CANDU spent fuel.Fusion Technol. 20: 26–39

    Google Scholar 

  • Şahin S, YapiciH, Baltacioglu E 1994 Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket.Kerntechnik, 59: 270–277

    Google Scholar 

  • Şahin S, YapiciH, Baltacioglu E 1998 Fusion breeder with enhanced safeguarding capabilities against nuclear weapon proliferation.Energy Conver. Manage. 39: 899–909

    Article  Google Scholar 

  • Şahin S, YapiciH, Bayrak M 1999 Spent mixed oxide fuel rejuvenation in fusion breeders.Fusion Eng. Design 47: 9–23

    Article  Google Scholar 

  • Şahin S, Özceyhan V, YapiciH 2001 a Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel.Ann. Nucl. Energy 28: 203–223

    Article  Google Scholar 

  • Şahin S, YapiciH, Şahin N 2001b Neutronic performance of proliferation hardened thorium fusion breeders.Fusion Eng. Design 54: 63–77

    Article  Google Scholar 

  • Şahin S, Yalçin Ş, Şahin H M, Übeyli M 2003a Neutronics analysis of HYLIFE-II blanket for fissile fuel breeding in an inertial fusion energy reactor.Ann. Nucl. Energy 30: 669–683

    Article  Google Scholar 

  • Şahin S, Yalçin Ş, Şahin H M, Übeyli M 2003b Neutronic Investigation of a hybrid version of the ARIES-RS fusion reactor.Ann. Nucl. Energy 30: 245–59

    Article  Google Scholar 

  • Smith D Let al 1985 Blanket comparison and selection study.Fusion Technol. 8: 10–44

    Google Scholar 

  • Smid I, Akiba M, Vieider G, Plöchl L 1998 Development of tungsten armor and bonding to copper for plasma-interactive components.J. Nucl. Mater. 258–263: 160–172

    Article  Google Scholar 

  • Sze D K, Moir R W, Zinkle S 1999 Database for liquid breeders and coolants.On the exploration of innovative concepts for fusion chamber technology (ed.) M Abdou, APEX Interim Report (Overview), UCLA-ENG-99-206, UCLA-FNT-107, University of California, Los Angeles, CA

    Google Scholar 

  • Übeyli M 2003 On the tritium breeding capability of Flibe, Flinabe and Li20Sn80 in a fusion-fission (hybrid) reactor.J. Fusion Energy 22: 51–57

    Article  Google Scholar 

  • Übeyli M 2004 Transmutation of minor actinides discharged from LMFBR spent fuel in a high power density fusion reactor.Energy Convers. Manage. (in press)

  • YapiciHet al 1999 Potential of a fusion-fission hybrid reactor using uranium for various coolants to breed fissile fuel for LWRs.Ann. Nucl. Energy 26: 821–823

    Article  Google Scholar 

  • YapiciH, Özceyhan V 2000 Numerical neutronic analysis of a natural lithium cooled fusion breeder fueled with UO2,Arabian J. Sci. Eng. 25(2A): 95–109

    Google Scholar 

  • YapiciH, Übeyli M, Yalçin Ş 2002 Neutronic analysis of Prometheus reactor fueled with various compounds of thorium and uranium.Ann. Nucl. Energy 29: 1871–1889

    Article  Google Scholar 

  • YapiciH, Ýpek O, Übeyli M 2003 Investigation of the performance parameters and temperature distribution in fuel rod dependent on operation periods and first wall loads in fusion-fission reactor system fueled with ThO2.Energy Conver. Manage. 44: 573–595

    Article  Google Scholar 

  • YapiciH, Übeyli M 2003 Power Flattening in Prometheus breeder reactor using nuclear fuel and waste actinide.Ann. Nucl. Energy 30: 159–173

    Article  Google Scholar 

  • Youssef M Z, Sawan M E, Sze D K 2002 The breeding potential of ‘flinabe’ and comparison to ‘flibe’ in ‘CLiFF’ high power density concept.Fusion Eng. Design 61–62: 497–503

    Article  Google Scholar 

  • Zinkle S J, Ghoniem N M 2000 Operating temperature windows for fusion reactor structural materials.Fusion Eng. Design 51–52: 55–71

    Article  Google Scholar 

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Authors and Affiliations

  1. Fen-Edebiyat Fakültesi, Bahçeşehir Üniversitesi, İstanbul, Turkey

    Senay Yalçin

  2. Mühendislik Fakültesi, TOBB Ekonomi ve Teknoloji Üniversitesi, Ankara, Turkey

    Mustafa Übeyli

  3. Teknik Egitim Fakültesi, Teknikokullar, Gazi Üniversitesi, Ankara, Turkey

    Adem Acir

Authors
  1. Senay Yalçin
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  2. Mustafa Übeyli
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  3. Adem Acir
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Correspondence to Mustafa Übeyli.

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Yalçin, S., Übeyli, M. & Acir, A. Neutronic analysis of a high power density hybrid reactor using innovative coolants. Sadhana 30, 585–600 (2005). https://doi.org/10.1007/BF02703281

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  • DOI: https://doi.org/10.1007/BF02703281

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