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Volumn 34, Issue 2, 1998, Pages 95-108

Neutronic calculations for a magnetic fusion energy reactor with liquid protection for the first wall

Author keywords

Liquid wall protection; Material damage; Shallow burial

Indexed keywords

BREEDING BLANKETS; GRAPHITE; LIQUID METAL COOLED REACTORS; LITHIUM; LITHIUM ALLOYS; LITHIUM COMPOUNDS; MAGNETIC FIELD EFFECTS; PLASMA CONFINEMENT; RADIATION DAMAGE; RADIATION PROTECTION; SILICON CARBIDE; STAINLESS STEEL;

EID: 0032166114     PISSN: 07481896     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST98-A56     Document Type: Article
Times cited : (27)

References (30)
  • 1
    • 0002400698 scopus 로고
    • Design for a High Power-Density Astron Reactor
    • N. C. CHRISTOHLOS, "Design for a High Power-Density Astron Reactor," J. Fusion Energy, 8, 97 (1989).
    • (1989) J. Fusion Energy , vol.8 , pp. 97
    • Christohlos, N.C.1
  • 2
    • 0023439005 scopus 로고
    • Rotating Liquid Blanket for a Toroidal Fusion Reactor
    • R. W. MOIR, "Rotating Liquid Blanket for a Toroidal Fusion Reactor," Fusion Eng. Des., 5, 269 (1987).
    • (1987) Fusion Eng. Des. , vol.5 , pp. 269
    • Moir, R.W.1
  • 3
    • 0029633981 scopus 로고
    • The Logic behind Thick, Liquid-Walled, Fusion Concepts
    • R. W. MOIR, "The Logic Behind Thick, Liquid-Walled, Fusion Concepts," Nucl. Eng. Des., 29, 34 (1995).
    • (1995) Nucl. Eng. Des. , vol.29 , pp. 34
    • Moir, R.W.1
  • 4
    • 0031120863 scopus 로고    scopus 로고
    • Liquid First Walls for Magnetic Fusion Energy Configurations
    • R. W. MOIR, "Liquid First Walls for Magnetic Fusion Energy Configurations," Nucl. Fusion, 37,4, 557 (1997).
    • (1997) Nucl. Fusion , vol.37 , Issue.4 , pp. 557
    • Moir, R.W.1
  • 5
    • 0030073939 scopus 로고    scopus 로고
    • Radiation Damage in Liquid Protected First-Wall Materials for IFE-Reactors
    • S. ŞAHlN, R. W. MOIR, A. SAHINASLAN, and H. M. SAHIN, "Radiation Damage in Liquid Protected First-Wall Materials for IFE-Reactors," Fusion Technol, 30, 1027 (1996).
    • (1996) Fusion Technol , vol.30 , pp. 1027
    • Şahln, S.1    Moir, R.W.2    Sahinaslan, A.3    Sahin, H.M.4
  • 6
    • 0028336175 scopus 로고
    • HYLIFE-II, A Molten-Salt Inertial Fusion Energy Power Plant Design-Final Report
    • R. W. MOIR et al., "HYLIFE-II, A Molten-Salt Inertial Fusion Energy Power Plant Design-Final Report," Fusion Technol, 25, 5 (1994).
    • (1994) Fusion Technol , vol.25 , pp. 5
    • Moir, R.W.1
  • 7
    • 0028546159 scopus 로고
    • HYLIFE-II Reactor Chamber Design Refinements
    • P. A. HOUSE, "HYLIFE-II Reactor Chamber Design Refinements," Fusion Technol, 26, 1178 (1994).
    • (1994) Fusion Technol , vol.26 , pp. 1178
    • House, P.A.1
  • 8
    • 0028483087 scopus 로고
    • Waste Disposal Assessment of HYLIFE-II Structure
    • J. D. LEE, "Waste Disposal Assessment of HYLIFE-II Structure," Fusion Technol., 26, 74 (1994).
    • (1994) Fusion Technol , vol.26 , pp. 74
    • Lee, J.D.1
  • 9
    • 0028741803 scopus 로고
    • Neutronic Investigation of a Power Plant Using Peaceful Nuclear Explosives
    • S. ŞAHlN, R. W. MOIR, and S. ÜNALAN, "Neutronic Investigation of a Power Plant Using Peaceful Nuclear Explosives," Fusion Technol., 26, 1311 (1994).
    • (1994) Fusion Technol , vol.26 , pp. 1311
    • Şahln, S.1    Moir, R.W.2    Ünalan, S.3
  • 12
    • 0001858160 scopus 로고
    • CLAW-IV Coupled 30 Neutrons, 12 Gamma-Ray Group Cross Sections with Retrieval Programs for Radiation Transport Calculations
    • Radiation Shield1ing Information Center May
    • T.A.AL-KUSAYER, S. SAHIN, and A. DRIRA, "CLAW-IV Coupled 30 Neutrons, 12 Gamma-Ray Group Cross Sections with Retrieval Programs for Radiation Transport Calculations," RSIC Newslett., p. 4, Radiation Shield1ing Information Center (May 1988).
    • (1988) RSIC Newslett , pp. 4
    • Al-Kusayer, T.A.1    Sahin, S.2    Drira, A.3
  • 14
    • 0015660574 scopus 로고
    • Comparison of Diffusion and Transport Theory for Fast Reactor Shielding Calculations
    • S. ŞAHIN, "Comparison of Diffusion and Transport Theory for Fast Reactor Shielding Calculations," Atomkernenergie, 22, 24 (1973).
    • (1973) Atomkernenergie , vol.22 , pp. 24
    • Şahin, S.1
  • 15
    • 0026202353 scopus 로고
    • Potential of a Catalyzed Fusion-Driven Hybrid Reactor for the Regeneration of CANDU Spent Fuel
    • S. ŞAHlN, E. BALTACIOǦLU, and H. YAPICI, "Potential of a Catalyzed Fusion-Driven Hybrid Reactor for the Regeneration of CANDU Spent Fuel," Fusion Technol, 20, 26 (1991).
    • (1991) Fusion Technol , vol.20 , pp. 26
    • Şahln, S.1    Baltacioǧlu, E.2    Yapici, H.3
  • 16
    • 0003674957 scopus 로고
    • UCRL-53559, K. L. ESSARY and K. E. LEWIS, Eds., Lawrence Livermore National Laboratory
    • A. BLINK et al., "High-Yield Lithium-Injection FusionEnergy (HYLIFE) Reactor," UCRL-53559, K. L. ESSARY and K. E. LEWIS, Eds., Lawrence Livermore National Laboratory (1985).
    • (1985) High-Yield Lithium-Injection FusionEnergy (HYLIFE) Reactor
    • Blink, A.1
  • 17
    • 0005441120 scopus 로고
    • Radiation Damage in Structural Materials
    • International Atomic Energy Agency
    • M. PERLADO, M. W. GUINAN, and K. ABE, "Radiation Damage in Structural Materials," Energy from Inertial Fusion, p. 272, International Atomic Energy Agency (1995).
    • (1995) Energy from Inertial Fusion , pp. 272
    • Perlado, M.1    Guinan, M.W.2    Abe, K.3
  • 21
    • 0002424689 scopus 로고    scopus 로고
    • Radioactive Waste Disposal Characteristics of Candidate Tokamak Demonstration Reactors
    • E. A. HOFFMAN, W. M. STACEY, and N. E. HERTEL, "Radioactive Waste Disposal Characteristics of Candidate Tokamak Demonstration Reactors," Fusion Technol., 31, 35 (1997).
    • (1997) Fusion Technol , vol.31 , pp. 35
    • Hoffman, E.A.1    Stacey, W.M.2    Hertel, N.E.3
  • 24
    • 31044439668 scopus 로고
    • UCID 17026, Rev. 3, Lawrence Livermore National Laboratory Jan.
    • R. KIMLINGER et al., "TART and ALICE Input Manual," UCID 17026, Rev. 3, Lawrence Livermore National Laboratory (Jan. 1990).
    • (1990) TART and ALICE Input Manual
    • Kimlinger, R.1
  • 26
    • 0022523973 scopus 로고
    • Key Design Features of the MARS Blanket and Shield
    • North-Holland, Amsterdam
    • M. E. SAWAN and I. N. SVIATOSLAVSKY, "Key Design Features of The MARS Blanket and Shield," Nucl. Eng. Des., 3, 203, North-Holland, Amsterdam (1986).
    • (1986) Nucl. Eng. Des. , vol.3 , pp. 203
    • Sawan, M.E.1    Sviatoslavsky, I.N.2
  • 27
    • 0020086851 scopus 로고
    • Issues in Radioactive Waste Management for Fusion Power
    • Feb.
    • R. C. MANINGER and D. W. DORN, "Issues in Radioactive Waste Management for Fusion Power," IEEE Trans. Nucl. Sci., NS-30,1, 571 (Feb. 1983).
    • (1983) IEEE Trans. Nucl. Sci. , vol.NS30 , Issue.1 , pp. 571
    • Maninger, R.C.1    Dorn, D.W.2
  • 28
    • 84925500762 scopus 로고
    • Licensing Requirements for Land Disposal of Radioactive Waste
    • 10 CFR 61, Nuclear Regulatory Commission
    • "Licensing Requirements for Land Disposal of Radioactive Waste," 10 CFR 61, Code of Federal Regulations, Nuclear Regulatory Commission (1982).
    • (1982) Code of Federal Regulations
  • 29
    • 0030074116 scopus 로고    scopus 로고
    • Shielding Analysis for Toroidal Field Coils Around Exhaust Duct in Fusion Experimental Reactors
    • S. SATO, K. MAKI, H. TAKATSU, and Y. SEKI, "Shielding Analysis for Toroidal Field Coils Around Exhaust Duct in Fusion Experimental Reactors," Fusion Technol., 30, 1076 (1996).
    • (1996) Fusion Technol , vol.30 , pp. 1076
    • Sato, S.1    Maki, K.2    Takatsu, H.3    Seki, Y.4
  • 30
    • 0026222345 scopus 로고
    • Definition of All Relevant Local Nuclear Responses and the Total Heating in the Toroidal Field Coils during the Conceptual Design Phase of ITER
    • S. A. ZIMIN, "Definition of All Relevant Local Nuclear Responses and the Total Heating in the Toroidal Field Coils During the Conceptual Design Phase of ITER," Fusion Technol., 20, 144 (1991).
    • (1991) Fusion Technol , vol.20 , pp. 144
    • Zimin, S.A.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.