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Volumn 2006, Issue , 2006, Pages 752-761

Low-temperature multiple-reheat closed gas power cycles for the AHTR and LSFR

Author keywords

[No Author keywords available]

Indexed keywords

BRAYTON CYCLE; GAS COOLED REACTORS; GAS TURBINES; REACTOR CORES; REHEAT CYCLE; THERMAL EFFECTS;

EID: 33845749206     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (7)

References (9)
  • 1
    • 2342645783 scopus 로고    scopus 로고
    • The gas turbine-modular helium reactor: A promising option for near term deployment
    • Embedded Topical American Nuclear Society 2002 Annual Meeting, Hollywood, Florida, USA, June 9-13
    • M. P., LABAR, "The Gas Turbine-Modular Helium Reactor: A Promising Option for Near Term Deployment," Proc., 2002 International Congress on Advanced Nuclear Power Plants (ICAPP'02), Embedded Topical American Nuclear Society 2002 Annual Meeting, Hollywood, Florida, USA, June 9-13, (2002).
    • (2002) Proc., 2002 International Congress on Advanced Nuclear Power Plants (ICAPP'02)
    • Labar, M.P.1
  • 2
    • 33745438508 scopus 로고    scopus 로고
    • Pebble Bed Modular Reactor (PBMR) project update
    • Embedded International Topical Meeting 2004 American Nuclear Society Annual Meeting, Pittsburg, Pennsylvania, USA, June 13-17
    • R.A., MATZIE, "Pebble Bed Modular Reactor (PBMR) Project Update," Proc., 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04), Embedded International Topical Meeting 2004 American Nuclear Society Annual Meeting, Pittsburg, Pennsylvania, USA, June 13-17, (2004).
    • (2004) Proc., 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04)
    • Matzie, R.A.1
  • 3
    • 0345604446 scopus 로고    scopus 로고
    • Multiple-reheat brayton cycles for nuclear power conversion with molten coolants
    • P. F., PETERSON, "Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants," Nucl. Technol., 144, 279-288 (2003).
    • (2003) Nucl. Technol. , vol.144 , pp. 279-288
    • Peterson, P.F.1
  • 4
  • 5
  • 6
    • 0345172386 scopus 로고    scopus 로고
    • Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity
    • C. W., FORS BERG, P. S., Pickard, and P. F., Peterson, "Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity," Nucl. Technol., 144, 289-302 (2003).
    • (2003) Nucl. Technol. , vol.144 , pp. 289-302
    • Fors Berg, C.W.1    Pickard, P.S.2    Peterson, P.F.3
  • 7
    • 33845731346 scopus 로고    scopus 로고
    • A flexible base-line design for the Advanced High-Temperature Reactor utilizing Metallic reactor Internals (AHTR-MI)
    • Embedded International Topical Meeting 2006 American Nuclear Society Annual Meeting, Reno, NV, USA, June 4-6
    • P.F. PETERSON and H. Zhao, "A Flexible Base-Line Design for the Advanced High-Temperature Reactor Utilizing Metallic Reactor Internals (AHTR-MI)," Proc., 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06), Embedded International Topical Meeting 2006 American Nuclear Society Annual Meeting, Reno, NV, USA, June 4-6, (2006).
    • (2006) Proc., 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06)
    • Peterson, P.F.1    Zhao, H.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.