메뉴 건너뛰기




Volumn 151, Issue 3, 2005, Pages 314-333

Inherent safety of fuels for accelerator-driven systems

Author keywords

Accelerator driven systems; Accidents; Minor actinide fuel

Indexed keywords

ACCIDENT PREVENTION; ACTINIDES; CERMETS; CRITICALITY (NUCLEAR FISSION); LOSS OF COOLANT ACCIDENTS; PARTICLE ACCELERATORS; REACTIVITY (NUCLEAR); REACTOR CORES;

EID: 23844448469     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT05-A3654     Document Type: Article
Times cited : (18)

References (58)
  • 1
    • 0242534578 scopus 로고
    • "Review of PNL Study on Transmutation Processing of High Level Waste"
    • LA-UR-74-74, Los Alamos Scientific Laboratory
    • D. G. FOSTER et al., "Review of PNL Study on Transmutation Processing of High Level Waste," LA-UR-74-74, Los Alamos Scientific Laboratory (1974).
    • (1974)
    • Foster, D.G.1
  • 3
    • 0037671246 scopus 로고    scopus 로고
    • "Neutronic Aspects of Inert Matrix Fuels for Application in ADS"
    • J. WALLENIUS, "Neutronic Aspects of Inert Matrix Fuels for Application in ADS," J. Nucl. Mater., 320 142 (2003).
    • (2003) J. Nucl. Mater. , vol.320 , pp. 142
    • Wallenius, J.1
  • 6
    • 33645263878 scopus 로고    scopus 로고
    • "Oxide and Nitride TRU-Fuels: Lessons Drawn from the CONFIRM and FUTURE Projects of the 5th European Framework Programme"
    • Nimes, France, June 21-24
    • S. PILLON and J. WALLENIUS, "Oxide and Nitride TRU-Fuels: Lessons Drawn from the CONFIRM and FUTURE Projects of the 5th European Framework Programme," Proc. ATALANTE 2004: Advances for Future Nuclear Fuel Cycles, Nimes, France, June 21-24, 2004.
    • (2004) Proc. ATALANTE 2004: Advances for Future Nuclear Fuel Cycles
    • Pillon, S.1    Wallenius, J.2
  • 7
    • 33645270511 scopus 로고    scopus 로고
    • "Neutronic Design of Minor Actinide Burning Accelerator-Driven Systems"
    • (to be published)
    • J. WALLENIUS and M. ERIKSSON, "Neutronic Design of Minor Actinide Burning Accelerator-Driven Systems," Nucl. Technol. (to be published).
    • Nucl. Technol.
    • Wallenius, J.1    Eriksson, M.2
  • 8
    • 5244242242 scopus 로고
    • "Safety Related Terms for Advanced Nuclear Plants"
    • IAEA-TECDOC-626, International Atomic Energy Agency (Sep.)
    • "Safety Related Terms for Advanced Nuclear Plants," IAEA-TECDOC-626, International Atomic Energy Agency (Sep. 1991).
    • (1991)
  • 9
    • 0002657127 scopus 로고
    • "Fission Reactor Studies in View of Reactor Waste Programmes"
    • H. MURATA and T. MUKAIYAMA, "Fission Reactor Studies in View of Reactor Waste Programmes," Atomkernenerg. Kerntech., 45, 23 (1984).
    • (1984) Atomkernenerg. Kerntech. , vol.45 , pp. 23
    • Murata, H.1    Mukaiyama, T.2
  • 10
    • 0033204063 scopus 로고    scopus 로고
    • "Selection of Materials as Diluents for Burning of Plutonium Fuels in Nuclear Reactors"
    • H. KLEYKAMP, "Selection of Materials as Diluents for Burning of Plutonium Fuels in Nuclear Reactors," J. Nucl. Mater., 275, 1 (1999).
    • (1999) J. Nucl. Mater. , vol.275 , pp. 1
    • Kleykamp, H.1
  • 16
    • 0038409853 scopus 로고    scopus 로고
    • "The Chemistry and Physics of Modeling Nitride Fuels for Transmutation"
    • R. THETFORD and M. MIGNANELLI, "The Chemistry and Physics of Modeling Nitride Fuels for Transmutation," J. Nucl. Mater., 320, 44 (2003).
    • (2003) J. Nucl. Mater. , vol.320 , pp. 44
    • Thetford, R.1    Mignanelli, M.2
  • 18
    • 0003497194 scopus 로고
    • Technical Information Center, Office of Public Affairs, Energy Research and Development Administration, Springfield, Virginia
    • D. R. OLANDER, Fundamental Aspects of Nuclear Reactor Elements, pp. 131-135, Technical Information Center, Office of Public Affairs, Energy Research and Development Administration, Springfield, Virginia (1976).
    • (1976) Fundamental Aspects of Nuclear Reactor Elements , pp. 131-135
    • Olander, D.R.1
  • 20
    • 0027042837 scopus 로고
    • "Behavior Under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly"
    • R. E. Stoller, A. S. Kumar, and D. S. Gelles, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania
    • J. L. SÉRAN, V. LÉVY, P. DUBUISSON, D. GILBON, A. MAILLARD, A. FISSOLO, H. TOURON, R. CAUVIN, A. CHALONY, and A. LE BOULBIN, "Behavior Under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly," Effects of Radiation on Materials: 15th Int. Symp., ASTM STP 1125, p. 1209, R. E. STOLLER, A. S. KUMAR, and D. S. GELLES, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania (1992).
    • (1992) Effects of Radiation on Materials: 15th Int. Symp., ASTM STP 1125 , pp. 1209
    • Séran, J.L.1    Lévy, V.2    Dubuisson, P.3    Gilbon, D.4    Maillard, A.5    Fissolo, A.6    Touron, H.7    Cauvin, R.8    Chalony, A.9    Le Boulbin, A.10
  • 21
    • 0028192821 scopus 로고
    • "Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels"
    • A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania
    • A. FISSOLO, V. LÈVY, J. L. SÈRAN, A. MAILLARD, J. ROYER, and O. ARBOUILLE, "Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels," Effects of Radiation on Materials: 16th Int. Symp., ASTM STP 1175, p. 646, A. S. KUMAR, D. S. GELLES, R. K. NANSTAD, and E. A. LITTLE, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania (1993).
    • (1993) Effects of Radiation on Materials: 16th Int. Symp., ASTM STP 1175 , pp. 646
    • Fissolo, A.1    Lèvy, V.2    Sèran, J.L.3    Maillard, A.4    Royer, J.5    Arbouille, O.6
  • 24
    • 33645267858 scopus 로고
    • "Fast Reactor Manual"
    • Fast Reactor European Collaboration Report
    • J. EDWARDS et al., "Fast Reactor Manual," Fast Reactor European Collaboration Report (1990).
    • (1990)
    • Edwards, J.1
  • 25
    • 33645258359 scopus 로고    scopus 로고
    • Personal Communication (Jan.)
    • R. KONINGS, Personal Communication (Jan. 2004).
    • (2004)
    • Konings, R.1
  • 27
    • 0031340744 scopus 로고    scopus 로고
    • "Melting Behaviour of Oxide Systems for Heterogeneous Transmutation of Actinides. III. The System Am-Mg-O"
    • H. ZHANG, R. J. M. KONINGS, M. E. HUNTELAAR, and E. H. P. CORDFUNKE, "Melting Behaviour of Oxide Systems for Heterogeneous Transmutation of Actinides. III. The System Am-Mg-O," J. Nucl. Mater., 250 88 (1997).
    • (1997) J. Nucl. Mater. , vol.250 , pp. 88
    • Zhang, H.1    Konings, R.J.M.2    Huntelaar, M.E.3    Cordfunke, E.H.P.4
  • 28
    • 0031247094 scopus 로고    scopus 로고
    • "Melting Behaviour of Oxide Systems for Heterogeneous Transmutation of Actinides. I. The Systems Pu-Al-O and Pu-Mg-O"
    • H. ZHANG, R. J. M. KONINGS, M. E. HUNTELAAR, and E. H. P. CORDFUNKE, "Melting Behaviour of Oxide Systems for Heterogeneous Transmutation of Actinides. I. The Systems Pu-Al-O and Pu-Mg-O," J. Nucl. Mater., 249 223 (1997).
    • (1997) J. Nucl. Mater. , vol.249 , pp. 223
    • Zhang, H.1    Konings, R.J.M.2    Huntelaar, M.E.3    Cordfunke, E.H.P.4
  • 29
    • 70350128637 scopus 로고    scopus 로고
    • "Synthesis of Americium Mononitride by Carbothermic Reduction Method"
    • Jackson Hole, Wyoming, August 29-September 3, American Nuclear Society (1999) (CD-ROM)
    • M. TAKANO, A. ITOH, M. AKABORI, T. OGAWA, S. KIKKAWA, and H. OKAMOTO, "Synthesis of Americium Mononitride by Carbothermic Reduction Method," Proc. Int. Conf. Future Nuclear Systems (GLOBAL '99), Jackson Hole, Wyoming, August 29-September 3, 1999, American Nuclear Society (1999) (CD-ROM).
    • (1999) Proc. Int. Conf. Future Nuclear Systems (GLOBAL '99)
    • Takano, M.1    Itoh, A.2    Akabori, M.3    Ogawa, T.4    Kikkawa, S.5    Okamoto, H.6
  • 30
    • 2942755880 scopus 로고    scopus 로고
    • "Thermo-Chemical Modelling of Uranium-Free Nitride Fuels"
    • M. JOLKKONEN, M. STREIT, and J. WALLENIUS, "Thermo-Chemical Modelling of Uranium-Free Nitride Fuels," J. Nucl. Sci. Technol., 41, 4, 457 (2004).
    • (2004) J. Nucl. Sci. Technol. , vol.41 , Issue.4 , pp. 457
    • Jolkkonen, M.1    Streit, M.2    Wallenius, J.3
  • 31
    • 0036613788 scopus 로고    scopus 로고
    • "Thermo-Calc and DICTRA, Computational Tools for Materials Science"
    • J.-O. ANDERSSON et al., "Thermo-Calc and DICTRA, Computational Tools for Materials Science," Calphad, 26, 273 (2002).
    • (2002) Calphad , vol.26 , pp. 273
    • Andersson, J.-O.1
  • 32
    • 0029326443 scopus 로고
    • "Vaporization Behaviour of (Pu, Am)N"
    • T. OGAWA et al., "Vaporization Behaviour of (Pu, Am)N," J. Alloys Compounds, 224, 55 (1995).
    • (1995) J. Alloys Compounds , vol.224 , pp. 55
    • Ogawa, T.1
  • 33
    • 0027044433 scopus 로고
    • "Transient and Static Mechanical Properties of D9 Fuel Pin Cladding and Duct Material Irradiated to High Fluence"
    • R. E. Stoller, A. S. Kumar, and D. S. Gelles, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania
    • N. S. CANNON, F. R. HUANG, and M. L. HAMILTON, "Transient and Static Mechanical Properties of D9 Fuel Pin Cladding and Duct Material Irradiated to High Fluence," Effects of Radiation on Materials: 15th Int. Symp., ASTM STP 1125, p. 1071, R. E. STOLLER, A. S. KUMAR, and D. S. GELLES, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania (1992).
    • (1992) Effects of Radiation on Materials: 15th Int. Symp., ASTM STP 1125 , pp. 1071
    • Cannon, N.S.1    Huang, F.R.2    Hamilton, M.L.3
  • 34
    • 0028259342 scopus 로고
    • "Mechanical Property Degradation of Fast Reactor Fuel Cladding During Thermal Transients"
    • ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania
    • I. SHIBAHARA, T. OMORI, Y. SATO, S. ONOSE, and S. NOMURA, "Mechanical Property Degradation of Fast Reactor Fuel Cladding During Thermal Transients," Effects of Radiation on Materials: 16th Int. Symp., ASTM STP 1175, p. 664, A. S. KUMAR, D. S. GELLES, R. NANSTAD, and E. A. LITTLE, Eds., American Society for Testing and Materials, Philadelphia, Pennsylvania (1994).
    • (1994) Effects of Radiation on Materials: 16th Int. Symp. , pp. 664
    • Shibahara, I.1    Omori, T.2    Sato, Y.3    Onose, S.4    Nomura, S.5
  • 35
    • 1642265912 scopus 로고
    • "Synergistic Tellurium-Caesium Embrittlement of Type 316 Stainless Steel"
    • M. G. ADAMSON, E. A. AITKEN, and S. VAIDYANATHAN, "Synergistic Tellurium-Caesium Embrittlement of Type 316 Stainless Steel," Nature, 295, 49 (1982).
    • (1982) Nature , vol.295 , pp. 49
    • Adamson, M.G.1    Aitken, E.A.2    Vaidyanathan, S.3
  • 36
    • 33645251696 scopus 로고
    • "Fuel Cladding Mechanical Property Degradation Mechanisms and Fuel Reliability Under Transient Conditions"
    • Tucson, Arizona, September 7-11, 1986, American Nuclear Society
    • S. TANI, S. NOMURA, and I. SHIBAHARA, "Fuel Cladding Mechanical Property Degradation Mechanisms and Fuel Reliability Under Transient Conditions," Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7-11, 1986, American Nuclear Society (1986).
    • (1986) Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors
    • Tani, S.1    Nomura, S.2    Shibahara, I.3
  • 38
    • 0002576405 scopus 로고    scopus 로고
    • "Problems of Structural Materials' Corrosion in Lead-Bismuth Coolant"
    • Obninsk, Russia, October 5-9, State Scientific Center of Russian Federation Institute of Physics and Power Engineering (1998)
    • G. S. YACHMENYOV, A. YE. RUSANOV, B. F. GROMOV, YU. S. BELOMYTSEV, N. S. SKVORTSOV, and A. P. DEMISHONKOV, "Problems of Structural Materials' Corrosion in Lead-Bismuth Coolant," Proc. Heavy Liquid Metal Coolants in Nuclear Technology, Obninsk, Russia, October 5-9, 1998, Vol. 1, p. 133, State Scientific Center of Russian Federation Institute of Physics and Power Engineering (1998).
    • (1998) Proc. Heavy Liquid Metal Coolants in Nuclear Technology , pp. 133
    • Yachmenyov, G.S.1    Rusanov, A.Y.2    Gromov, B.F.3    Belomytsev, Yu.S.4    Skvortsov, N.S.5    Demishonkov, A.P.6
  • 39
    • 0003395844 scopus 로고    scopus 로고
    • "MCNP - A General Monte Carlo N-Particle Transport Code"
    • LA-13709-M, J. F. Briesmeister Ed., Los Alamos National Laboratory
    • "MCNP - A General Monte Carlo N-Particle Transport Code," LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000).
    • (2000)
  • 40
    • 0008908298 scopus 로고
    • "Advanced LMR Safety Analysis Capabilities in the SASSYS-1 and SAS4A Computer Codes"
    • Pittsburgh, Pennsylvania, April 17-21, American Nuclear Society (1994)
    • J. E. CAHALAN, A. M. TENTNER, and E. E. MORRIS, "Advanced LMR Safety Analysis Capabilities in the SASSYS-1 and SAS4A Computer Codes," Proc. Int. Topl. Mtg. Advanced Reactors Safety, Pittsburgh, Pennsylvania, April 17-21, 1994, American Nuclear Society (1994).
    • (1994) Proc. Int. Topl. Mtg. Advanced Reactors Safety
    • Cahalan, J.E.1    Tentner, A.M.2    Morris, E.E.3
  • 41
    • 14544271669 scopus 로고    scopus 로고
    • "On the Performance of Point Kinetics for the Analysis of Accelerator-Driven Systems"
    • M. ERIKSSON, J. E. CAHALAN, and W. S. YANG, "On the Performance of Point Kinetics for the Analysis of Accelerator-Driven Systems," Nucl. Sci. Eng., 149, 298 (2005).
    • (2005) Nucl. Sci. Eng. , vol.149 , pp. 298
    • Eriksson, M.1    Cahalan, J.E.2    Yang, W.S.3
  • 42
    • 1542305431 scopus 로고    scopus 로고
    • "Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinides"
    • K. TSUJIMOTO, T. SASA, K. NISHIHARA, H. OIGAWA, and H. TAKANO, "Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinides," J. Nucl. Sci. Technol., 41, 21 (2004).
    • (2004) J. Nucl. Sci. Technol. , vol.41 , pp. 21
    • Tsujimoto, K.1    Sasa, T.2    Nishihara, K.3    Oigawa, H.4    Takano, H.5
  • 43
    • 33645271258 scopus 로고    scopus 로고
    • "Hydrodynamics and Heat Transfer in Reactor Cooled by Lead-Bismuth Alloy"
    • Obninsk, Russia, October 5-9, 1998, State Scientific Center of Russian Federation Institute of Physics and Power Engineering
    • P. A. USHAKOV, "Hydrodynamics and Heat Transfer in Reactor Cooled by Lead-Bismuth Alloy," Proc. Heavy Liquid Metal Coolants in Nuclear Technology, Obninsk, Russia, October 5-9, 1998, Vol. 2, p. 612, State Scientific Center of Russian Federation Institute of Physics and Power Engineering (1998).
    • (1998) Proc. Heavy Liquid Metal Coolants in Nuclear Technology , vol.2 , pp. 612
    • Ushakov, P.A.1
  • 45
    • 0041755498 scopus 로고
    • "A Design Study for Inherent Safety Core, Aseismicity and Heat Transport System in Lead-Cooled Nitride-Fuel Fast Reactor"
    • Pittsburgh, Pennsylvania, April 17-21, American Nuclear Society (1994)
    • H. TAKANO, H. AKIE, T. HIRAOKA, K. NAKAMURA, K. HIROTA, and Y. KAMISHIMA, "A Design Study for Inherent Safety Core, Aseismicity and Heat Transport System in Lead-Cooled Nitride-Fuel Fast Reactor," Proc. Int. Topl. Mtg. Advanced Reactors Safety, Pittsburgh, Pennsylvania, April 17-21, 1994, American Nuclear Society (1994).
    • (1994) Proc. Int. Topl. Mtg. Advanced Reactors Safety
    • Takano, H.1    Akie, H.2    Hiraoka, T.3    Nakamura, K.4    Hirota, K.5    Kamishima, Y.6
  • 46
    • 0442280333 scopus 로고    scopus 로고
    • "Seismic Analysis of Heavy-Liquid-Metal-Cooled Reactor Vessels"
    • J. BUONGIORNO and B. D. HAWKES, "Seismic Analysis of Heavy-Liquid-Metal-Cooled Reactor Vessels," Nucl. Eng. Des., 228, 305 (2004).
    • (2004) Nucl. Eng. Des. , vol.228 , pp. 305
    • Buongiorno, J.1    Hawkes, B.D.2
  • 47
    • 0442296230 scopus 로고    scopus 로고
    • "Investigation upon the Dynamic Structural Response of a Nuclear Plant on Aseismic Isolating Devices"
    • I. MICHELI, S. CARDINI, A. COLAIUDA, and P. TURRONI, "Investigation upon the Dynamic Structural Response of a Nuclear Plant on Aseismic Isolating Devices," Nucl. Eng. Des., 228, 319 (2004).
    • (2004) Nucl. Eng. Des. , vol.228 , pp. 319
    • Micheli, I.1    Cardini, S.2    Colaiuda, A.3    Turroni, P.4
  • 48
    • 0036722236 scopus 로고    scopus 로고
    • "Inherent Shutdown Capabilities in Accelerator-Driven Systems"
    • M. ERIKSSON and J. E. CAHALAN, "Inherent Shutdown Capabilities in Accelerator-Driven Systems," Ann. Nucl. Energy, 29, 14, 1689 (2002).
    • (2002) Ann. Nucl. Energy , vol.29 , Issue.14 , pp. 1689
    • Eriksson, M.1    Cahalan, J.E.2
  • 50
    • 3142694262 scopus 로고    scopus 로고
    • "Coolant Void Worths in Fast Breeder Reactors and Accelerator Driven Transuranium and Minor Actinide Burners"
    • (to be published)
    • K. TUCEK, J. WALLENIUS, and W. GUDOWSKI, "Coolant Void Worths in Fast Breeder Reactors and Accelerator Driven Transuranium and Minor Actinide Burners," Ann. Nucl. Energy (to be published).
    • Ann. Nucl. Energy
    • Tucek, K.1    Wallenius, J.2    Gudowski, W.3
  • 51
    • 0012481078 scopus 로고    scopus 로고
    • "Safety Analysis of Nitride Fuels in Cores Dedicated to Waste Transmutation"
    • Madrid, Spain, December 11-13, Organization for Economic Cooperation and Development/Nuclear Energy Agency (2000)
    • J. WALLENIUS, K. TUCEK, and W. GUDOWSKI, "Safety Analysis of Nitride Fuels in Cores Dedicated to Waste Transmutation," Proc. 6th Information Exchange Mtg. Actinide and Fission Product Partitioning and Transmutation, Madrid, Spain, December 11-13, 2000, Organization for Economic Cooperation and Development/Nuclear Energy Agency (2000).
    • (2000) Proc. 6th Information Exchange Mtg. Actinide and Fission Product Partitioning and Transmutation
    • Wallenius, J.1    Tucek, K.2    Gudowski, W.3
  • 52
    • 33645261650 scopus 로고    scopus 로고
    • "Behavior of Transmuter Fuels of Accelerator Driven Systems under Severe Accident Conditions"
    • Kyoto, Japan, September 15-19
    • W. MASCHEK, T. SUZUKI, X. CHEN, M. G. MORI, C. M. BOCCACCINI, M. FLAD, and K. MORITA, "Behavior of Transmuter Fuels of Accelerator Driven Systems under Severe Accident Conditions," Proc. GENES4/ ANP2003, Kyoto, Japan, September 15-19, 2003.
    • (2003) Proc. GENES4/ANP2003
    • Maschek, W.1    Suzuki, T.2    Chen, X.3    Mori, M.G.4    Boccaccini, C.M.5    Flad, M.6    Morita, K.7
  • 53
    • 33645268016 scopus 로고    scopus 로고
    • "Estimates of Thermal Fatigue due to Beam Interruptions for an ALMR-Type ATW"
    • Aix-en-Provence, France, November 22-24, Nuclear Energy Agency/ Organization for Economic Cooperation and Development (1999)
    • F. E. DUNN and D. C. WADE, "Estimates of Thermal Fatigue due to Beam Interruptions for an ALMR-Type ATW," Proc. 2nd Int. Workshop Utilisation and Reliability of High Power Proton Accelerators, Aix-en-Provence, France, November 22-24, 1999, Nuclear Energy Agency/ Organization for Economic Cooperation and Development (1999).
    • (1999) Proc. 2nd Int. Workshop Utilisation and Reliability of High Power Proton Accelerators
    • Dunn, F.E.1    Wade, D.C.2
  • 54
    • 2642587454 scopus 로고    scopus 로고
    • "Reliability Assessment of the LANSCE Accelerator System"
    • MSc Thesis, Royal Institute of Technology, Department of Nuclear and Reactor Physics (Nov.)
    • M. ERIKSSON, "Reliability Assessment of the LANSCE Accelerator System," MSc Thesis, Royal Institute of Technology, Department of Nuclear and Reactor Physics (Nov. 1998).
    • (1998)
    • Eriksson, M.1
  • 55
    • 33645258656 scopus 로고    scopus 로고
    • "Active and Passive Safety Control Performance in Sub-Critical, Accelerator-Driven Nuclear Reactors"
    • Santa Fe, New Mexico, May, Nuclear Energy Agency/Organization for Economic Cooperation and Development (2002)
    • J. E. CAHALAN and M. ERIKSSON, "Active and Passive Safety Control Performance in Sub-Critical, Accelerator-Driven Nuclear Reactors," Proc. 3rd Int. Workshop Utilisation and Reliability of High Power Proton Accelerators, Santa Fe, New Mexico, May 2002, Nuclear Energy Agency/Organization for Economic Cooperation and Development (2002).
    • (2002) Proc. 3rd Int. Workshop Utilisation and Reliability of High Power Proton Accelerators
    • Cahalan, J.E.1    Eriksson, M.2
  • 57
    • 33645250835 scopus 로고    scopus 로고
    • "Safety Analyses for ADS Cores with Dedicated Fuel and Proposals for Safety Improvements"
    • IAEA-TECDOC-1356, International Atomic Energy Agency
    • W. MASCHEK et al., "Safety Analyses for ADS Cores with Dedicated Fuel and Proposals for Safety Improvements," IAEA-TECDOC-1356, International Atomic Energy Agency (2000).
    • (2000)
    • Maschek, W.1
  • 58
    • 33645265292 scopus 로고    scopus 로고
    • "The Analysis of Operating Experience of Reactor Installations Using Lead-Bismuth Coolant and Accidents Happened"
    • Obninsk, Russia, October 5-9, State Scientific Center of Russian Federation Institute of Physics and Power Engineering (1998)
    • B. F. GROMOV, O. G. GRIGORIEV, A. V. DEDOUL, G. I. TOSHINSKY, and V. S. STEPANOV, "The Analysis of Operating Experience of Reactor Installations Using Lead-Bismuth Coolant and Accidents Happened," Proc. Heavy Liquid Metal Coolants in Nuclear Technology, Obninsk, Russia, October 5-9, 1998, Vol. 1, p. 60, State Scientific Center of Russian Federation Institute of Physics and Power Engineering (1998).
    • (1998) Proc. Heavy Liquid Metal Coolants in Nuclear Technology , vol.1 , pp. 60
    • Gromov, B.F.1    Grigoriev, O.G.2    Dedoul, A.V.3    Toshinsky, G.I.4    Stepanov, V.S.5


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.