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Volumn 5, Issue , 2008, Pages 3279-3287

Liquid salt applications and molten salt reactors

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDE-BURNING; BRAYTON; BRAYTON GAS; EFFICIENT METHODS; ELECTRICITY PRODUCTION; FUSION MACHINES; HEAT TRANSPORT; HIGH TEMPERATURES; HIGH-TEMPERATURE SYSTEMS; HYDROGEN PRODUCTION SYSTEMS; INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS; LIQUID COOLANTS; LIQUID SALT COOLANT; METAL-CLAD; MOLTEN SALT REACTOR; MOLTEN SALT REACTORS; MOLTEN-SALT COOLANTS; NEW APPLICATIONS; NITRATE SALTS; NUCLEAR APPLICATIONS; NUCLEAR RENAISSANCE; NUCLEAR SYSTEMS; OIL PROCESSING; OIL REFINERIES; OPERATING TEMPERATURES; POWER DENSITIES; RAPID GROWTH; REACTOR CONCEPTS; STEAM CYCLES; TEMPERATURE LIMITS; TURBINE TECHNOLOGIES;

EID: 52249113941     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (15)

References (17)
  • 3
    • 52249123211 scopus 로고    scopus 로고
    • P. F. Peterson, H. Zhao, and G. Fukuda, Comparison of Molten Salt and High-Pressure Helium for the NGNP Intermediate Heat Transfer Fluid, UCBTH-03-004 (Rev. B), University of California at Berkeley, Berkeley, California (December, 2003).
    • P. F. Peterson, H. Zhao, and G. Fukuda, Comparison of Molten Salt and High-Pressure Helium for the NGNP Intermediate Heat Transfer Fluid, UCBTH-03-004 (Rev. B), University of California at Berkeley, Berkeley, California (December, 2003).
  • 4
    • 52249109490 scopus 로고    scopus 로고
    • D. F. Williams, L. M. Toth, and K. T. Clarno, Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR), ORNL/TM-2006/12, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2006).
    • D. F. Williams, L. M. Toth, and K. T. Clarno, Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR), ORNL/TM-2006/12, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2006).
  • 5
    • 52249095029 scopus 로고    scopus 로고
    • D. F. Williams, D. F., Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat Transfer Loop, ORNL/TM-2006/69, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2006).
    • D. F. Williams, D. F., "Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat Transfer Loop", ORNL/TM-2006/69, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2006).
  • 7
    • 55849110450 scopus 로고    scopus 로고
    • Use of Liquid Salt-Coolants to Improve Fast-Reactor Economics
    • Boston, Massachusetts June 24-28
    • C. W. Forsberg, "Use of Liquid Salt-Coolants to Improve Fast-Reactor Economics," American Nuclear Society Annual Meeting, Boston, Massachusetts (June 24-28, 2007).
    • (2007) American Nuclear Society Annual Meeting
    • Forsberg, C.W.1
  • 8
    • 79952208154 scopus 로고    scopus 로고
    • Trade Studies on the Liquid-Salt-Cooled Very High-Temperature Reactor
    • ORNL/TM 2006/140, Oak Ridge National Laboratory, Oak Ridge, Tennessee
    • D. T. Ingersoll, C. W. Forsberg, and P. E. MacDonald, Trade Studies on the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report, ORNL/TM 2006/140, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2006).
    • (2006) Fiscal Year 2006 Progress Report
    • Ingersoll, D.T.1    Forsberg, C.W.2    MacDonald, P.E.3
  • 11
    • 34249013705 scopus 로고    scopus 로고
    • The MOST Project: Key-points and Challenges for the Feasibility of Molten Salt Reactors
    • Paper 5208, Seoul, Korea, May 15-19
    • C. Renault et al, "The MOST Project: Key-points and Challenges for the Feasibility of Molten Salt Reactors", Paper 5208, Proceedings of ICAPP'05, Seoul, Korea, May 15-19, 2005 (2005).
    • (2005) Proceedings of ICAPP'05
    • Renault, C.1
  • 12
    • 44649128242 scopus 로고    scopus 로고
    • Proposal for a Simplified Thorium Molten Salt Reactor
    • Paper 428, Tsukuba, Japan, October 9-13, 2005
    • L. Mathieu et al., "Proposal for a Simplified Thorium Molten Salt Reactor", Paper 428, Proceedings of GLOBAL 2005, Tsukuba, Japan, October 9-13, 2005 (2005).
    • (2005) Proceedings of GLOBAL
    • Mathieu, L.1
  • 13
    • 52249116226 scopus 로고    scopus 로고
    • Fast Thorium Molten Salt Reactors Starting with Plutonium
    • Paper 6132, Reno, Nevada, June 4-8, American Nuclear Society
    • E. Merle-Lucotte et al., "Fast Thorium Molten Salt Reactors Starting with Plutonium," Paper 6132, Proc. International Conference on Advances in Nuclear Power Plants, Reno, Nevada, June 4-8, 2006. American Nuclear Society (2006).
    • (2006) Proc. International Conference on Advances in Nuclear Power Plants
    • Merle-Lucotte, E.1
  • 15
    • 45149120241 scopus 로고    scopus 로고
    • Results of Transient Analyses of the MOSART Molten Salt Reactor Design
    • Vienna, Austria, 28-30 November
    • M. Schikorr, "Results of Transient Analyses of the MOSART Molten Salt Reactor Design", presented at IAEA-CRP - Domain VI Meeting, Vienna, Austria, 28-30 November 2005.
    • (2005) presented at IAEA-CRP - Domain VI Meeting
    • Schikorr, M.1
  • 16
    • 0028336175 scopus 로고
    • HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design-Final Report
    • January
    • R. W. Moir et al., "HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design-Final Report," Fusion Technology, 25, 1, 5-25 (January 1994).
    • (1994) Fusion Technology , vol.25 , Issue.1 , pp. 5-25
    • Moir, R.W.1
  • 17
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    • Design Methods for Thick-Liquid Protection of Inertial Fusion Chambers
    • P. F. Peterson, "Design Methods for Thick-Liquid Protection of Inertial Fusion Chambers," Fusion Technology, 39, 2, 702-710 (2001).
    • (2001) Fusion Technology , vol.39 , Issue.2 , pp. 702-710
    • Peterson, P.F.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.