메뉴 건너뛰기




Volumn , Issue , 2004, Pages 349-363

The next generation nuclear plant - Insights gained from the INEEL point design studies

Author keywords

[No Author keywords available]

Indexed keywords

CONDUCTION COOLDOWN; COOLANT FLOW; GAS TURBINE-MODULAR HELIUM REACTOR (GT-MHR); HIGH TEMPERATURE GAS REACTORS (HTGR);

EID: 14844306759     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (10)

References (30)
  • 5
    • 0034246217 scopus 로고    scopus 로고
    • Status of the pebble bed modular reactor
    • D. R. NICHOLLS, "Status of the pebble bed modular reactor," Nuclear Energy 39, No. 4, pp. 231-236, (2000).
    • (2000) Nuclear Energy , vol.39 , Issue.4 , pp. 231-236
    • Nicholls, D.R.1
  • 8
    • 14844328424 scopus 로고
    • CEGA-002928, Rev. N/C, General Atomics, (November)
    • R. KAPERNICK, POKE User's Manual, CEGA-002928, Rev. N/C, General Atomics, (November 1993).
    • (1993) POKE User's Manual
    • Kapernick, R.1
  • 9
    • 2642579616 scopus 로고    scopus 로고
    • Idaho National Engineering and Environmental Laboratory, INEEL-EXT-98-00834, Revision 2.1, (April)
    • The RELAP5-3D Code Development Team, RELAP5-3D Code Manual, Idaho National Engineering and Environmental Laboratory, INEEL-EXT-98-00834, Revision 2.1, (April 2003).
    • (2003) RELAP5-3D Code Manual
  • 11
    • 22344454133 scopus 로고    scopus 로고
    • contributed by Los Alamos National Laboratory, Los Alamos, New Mexico, April and distributed as package CCC-660 by Oak Ridge National Laboratory
    • "MCNP4B: Monte Carlo N-Particle Transport Code System," contributed by Los Alamos National Laboratory, Los Alamos, New Mexico, April 1997 and distributed as package CCC-660 by Oak Ridge National Laboratory.
    • (1997) MCNP4B: Monte Carlo N-particle Transport Code System
  • 12
    • 1842733171 scopus 로고    scopus 로고
    • contributed by Los Alamos National Laboratory, Los Alamos, New Mexico, February 29, and distributed as package CCC-700 by Oak Ridge National Laboratory
    • "MCNP4C Monte Carlo N-Particle Transport Code System", contributed by Los Alamos National Laboratory, Los Alamos, New Mexico, February 29, 2000 and distributed as package CCC-700 by Oak Ridge National Laboratory.
    • (2000) MCNP4C Monte Carlo N-particle Transport Code System
  • 14
    • 14844329974 scopus 로고
    • EG&G Idaho, Inc., Idaho National Engineering Laboratory, presented at the 1994 Topical Meeting on Advances in Reactor Physics, Knoxville, TN, (April 11-15)
    • R. S. BABCOCK, D. E. WESSOL, C. A. WEMPLE, and S. C. MASON, The MOCUP Interface: A Coupled Monte Carlo/Depletion System, EG&G Idaho, Inc., Idaho National Engineering Laboratory, presented at the 1994 Topical Meeting on Advances in Reactor Physics, Vol. III, Knoxville, TN, (April 11-15, 1994).
    • (1994) The MOCUP Interface: A Coupled Monte Carlo/Depletion System , vol.3
    • Babcock, R.S.1    Wessol, D.E.2    Wemple, C.A.3    Mason, S.C.4
  • 16
    • 14844301531 scopus 로고    scopus 로고
    • Development of a supercritical carbon dioxide brayton cycle: Improving PBR efficiency and testing material compatibility
    • September
    • C. OH, T. LILLO, W. WINDES, T. TOTEMEIER, and R. MOORE, "Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving PBR Efficiency and Testing Material Compatibility", NERI Annual Report for Project 02-190, (September 2003).
    • (2003) NERI Annual Report for Project , vol.2 , Issue.190
    • Oh, C.1    Lillo, T.2    Windes, W.3    Totemeier, T.4    Moore, R.5
  • 18
    • 0036643027 scopus 로고    scopus 로고
    • Direct deterministic method for neutronics analysis and computation of asymptotic burnup distribution in a recirculating pebble-bed reactor
    • W. K. TERRY, H. D. GOUGAR, and A. M. OUGOUAG, "Direct Deterministic Method for Neutronics Analysis and Computation of Asymptotic Burnup Distribution in a Recirculating Pebble-Bed Reactor," Annals of Nuclear Energy 29, pp. 1345-1364, (2002).
    • (2002) Annals of Nuclear Energy , vol.29 , pp. 1345-1364
    • Terry, W.K.1    Gougar, H.D.2    Ougouag, A.M.3
  • 22
    • 22344457147 scopus 로고    scopus 로고
    • Optimal moderation in the pebble-bed reactor for enhanced passive safety and improved fuel utilization
    • Chicago April 26-29
    • ABDERRAFI M. OUGOUAG, HANS D. GOUGAR, WILLIAM K. TERRY, RAMATSEMELA MPHAHLELE, and KOSTADIN N. IVANOV "Optimal Moderation in the Pebble-Bed Reactor for Enhanced Passive Safety and Improved Fuel Utilization" Proceedings of PHYSOR-2004, Chicago April 26-29, 2004.
    • (2004) Proceedings of PHYSOR-2004
    • Ougouag, A.M.1    Gougar, H.D.2    Terry, W.K.3    Mphahlele, R.4    Ivanov, K.N.5
  • 27
    • 14844320899 scopus 로고    scopus 로고
    • Characteristics of a new pebble bed core with horizontal flow and comparison with the existing vertical flow core
    • Y. MUTO, "Characteristics of a New Pebble Bed Core with Horizontal Flow and Comparison with the Existing Vertical Flow Core", Proceedings of ICAPP 2004.
    • Proceedings of ICAPP 2004
    • Muto, Y.1
  • 29
    • 0342757337 scopus 로고
    • Results of experiments at the AVR reactor
    • H. GOTTAUT and K. KRUGER, "Results of Experiments at the AVR Reactor", Nuclear Engineering and Design, Vol. 121, pp 143-153, (1990).
    • (1990) Nuclear Engineering and Design , vol.121 , pp. 143-153
    • Gottaut, H.1    Kruger, K.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.