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Volumn 1, Issue , 2005, Pages 508-515

Lead-cooled, long-life fast reactor concepts for remote deployment

Author keywords

[No Author keywords available]

Indexed keywords

AUTONOMOUS CONTROL; FUEL INVENTORY; LEAD COOLED FAST REACTOR (LFR); NEUTRONICS; SMALL SECURE TRANSPORTABLE AUTONOMOUS REACTOR (SSTAR);

EID: 34249057751     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (7)

References (11)
  • 3
    • 4344642619 scopus 로고    scopus 로고
    • Neutronics Designs for a Lead Cooled, Small Modular Reactor Fueled with TRU
    • M. A. Smith, W. S. Yang, and T. A. Taiwo, "Neutronics Designs for a Lead Cooled, Small Modular Reactor Fueled with TRU," Trans. Am. Nucl. Soc., 90, 48-49 (2004).
    • (2004) Trans. Am. Nucl. Soc , vol.90 , pp. 48-49
    • Smith, M.A.1    Yang, W.S.2    Taiwo, T.A.3
  • 4
    • 22344447310 scopus 로고    scopus 로고
    • The Secure, Transportable, Autonomous Reactor System
    • 99, Jackson Hole, Wyoming, August 29, September 3
    • N. W. Brown, et al., "The Secure, Transportable, Autonomous Reactor System," Proc. of Intl. Conf. on Future Nuclear Systems, GLOBAL'99, Jackson Hole, Wyoming, August 29 - September 3, 1999.
    • (1999) Proc. of Intl. Conf. on Future Nuclear Systems, GLOBAL
    • Brown, N.W.1
  • 5
    • 22344446603 scopus 로고    scopus 로고
    • Neutronics Core Development of Small, Simplified, Proliferation-Resistant Reactor
    • 99, Jackson Hole, Wyoming, August 29, September 3
    • R. N. Hill, D. C. Wade, J. E. Cahalan, and H. S. Khalil, "Neutronics Core Development of Small, Simplified, Proliferation-Resistant Reactor," Proc. of Intl. Conf. on Future Nuclear Systems, GLOBAL'99, Jackson Hole, Wyoming, August 29 - September 3, 1999.
    • (1999) Proc. of Intl. Conf. on Future Nuclear Systems, GLOBAL
    • Hill, R.N.1    Wade, D.C.2    Cahalan, J.E.3    Khalil, H.S.4
  • 6
    • 0842312835 scopus 로고
    • MC2-2: A Code to Calculate Fast Neutron Spectra and Multigroup Cross Sections
    • Argonne National Laboratory
    • H. Henryson II, B. J. Toppel, and C. G. Stenberg, "MC2-2: A Code to Calculate Fast Neutron Spectra and Multigroup Cross Sections," ANL-8144, Argonne National Laboratory (1976).
    • (1976) ANL-8144
    • Henryson II, H.1    Toppel, B.J.2    Stenberg, C.G.3
  • 7
    • 33744651763 scopus 로고
    • DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems
    • Argonne National Laboratory
    • K. L. Derstine, "DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems," ANL-82-64, Argonne National Laboratory (1984).
    • (1984) ANL-82-64
    • Derstine, K.L.1
  • 8
    • 33847179305 scopus 로고
    • The DIF3D Nodal Neutronics Option for Two- and Three-Dimensional Diffusion Theory Calculations in Hexagonal Geometry
    • Argonne National Laboratory
    • R. D. Lawrence, "The DIF3D Nodal Neutronics Option for Two- and Three-Dimensional Diffusion Theory Calculations in Hexagonal Geometry," ANL-83-1, Argonne National Laboratory (1983).
    • (1983) ANL-83-1
    • Lawrence, R.D.1
  • 9
    • 1842603493 scopus 로고
    • A User's Guide to the REBUS-3 Fuel Cycle Analysis Capability
    • Argonne National Laboratory
    • B. J. Toppel, "A User's Guide to the REBUS-3 Fuel Cycle Analysis Capability," ANL-83-2, Argonne National Laboratory (1983).
    • (1983) ANL-83-2
    • Toppel, B.J.1
  • 10
    • 33847237102 scopus 로고
    • Specifications for VARI3D - A Multidimensional Reactor Design Sensitivity Code
    • Argonne National Laboratory
    • C. H. Adams, "Specifications for VARI3D - A Multidimensional Reactor Design Sensitivity Code," FRA-TM-74, Argonne National Laboratory (1975).
    • (1975) FRA-TM-74
    • Adams, C.H.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.