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Volumn 50, Issue 2-6, 2008, Pages 129-139

Innovations in the ENHS reactor design and fuel cycle

Author keywords

Enhanced power; Equilibrium cycle; Lead alloy cooled fast reactor; Minor actinides; Nuclear battery; Void coefficient

Indexed keywords

ACTINIDES; COOLANTS; HEAT EXCHANGERS; INNOVATION; NUCLEAR FUELS; OPTIMIZATION; RECYCLING;

EID: 39549123794     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2007.10.022     Document Type: Article
Times cited : (19)

References (18)
  • 1
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    • Fratoni, M., Kim, L., Mattafirri, S., Petroski, R., Greenspan, E., 2007. Preliminary feasibility study of the heat-pipe ENHS Reactor. In: Proceedings of International Conference on Emerging Nuclear Energy Systems, ICENES 2007, Istanbul, Turkey, June 3-8.
    • Fratoni, M., Kim, L., Mattafirri, S., Petroski, R., Greenspan, E., 2007. Preliminary feasibility study of the heat-pipe ENHS Reactor. In: Proceedings of International Conference on Emerging Nuclear Energy Systems, ICENES 2007, Istanbul, Turkey, June 3-8.
  • 2
    • 39549093710 scopus 로고    scopus 로고
    • Greenspan, E., and the ENHS Project Team, 2002. The long-life core encapsulated nuclear heat source (ENHS) generation IV reactor. In: Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Holywood, FL, June 9-13.
    • Greenspan, E., and the ENHS Project Team, 2002. The long-life core encapsulated nuclear heat source (ENHS) generation IV reactor. In: Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Holywood, FL, June 9-13.
  • 3
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    • Greenspan, E., April 2005. Solid-core heat-pipe nuclear battery type reactor. Research Proposal Submitted for the DOE Nuclear Engineering Education Research (NEER) Program.
    • Greenspan, E., April 2005. Solid-core heat-pipe nuclear battery type reactor. Research Proposal Submitted for the DOE Nuclear Engineering Education Research (NEER) Program.
  • 4
    • 39549114947 scopus 로고    scopus 로고
    • Greenspan, E., 2006. ENHS general information, technical features, and operating characteristics. IAEA Status Report on Innovative Small and Medium-Sized Reactors (SMRs).
    • Greenspan, E., 2006. ENHS general information, technical features, and operating characteristics. IAEA Status Report on Innovative Small and Medium-Sized Reactors (SMRs).
  • 5
    • 14644437830 scopus 로고    scopus 로고
    • The encapsulated nuclear heat source (ENHS) reactor core design
    • Hong S.G., Greenspan E., and Kim Y.I. The encapsulated nuclear heat source (ENHS) reactor core design. Nuclear Technology 149 (2005)
    • (2005) Nuclear Technology , vol.149
    • Hong, S.G.1    Greenspan, E.2    Kim, Y.I.3
  • 7
    • 39549115170 scopus 로고    scopus 로고
    • Hong, S.G., Greenspan, E., 2004. Power flattening options for the ENHS (encapsulated nuclear heat source) core. In: Proceedings of the International Symposium on Innovative Nuclear Energy Systems, Tokyo, Japan, October 31-November 4.
    • Hong, S.G., Greenspan, E., 2004. Power flattening options for the ENHS (encapsulated nuclear heat source) core. In: Proceedings of the International Symposium on Innovative Nuclear Energy Systems, Tokyo, Japan, October 31-November 4.
  • 8
    • 39549115369 scopus 로고    scopus 로고
    • Hong, S.G., Greenspan, E., 2005. Use of minor actinides for reduced power ENHS reactor core design. In: Proceedings of GLOBAL'05, Tsukuba, Japan, October 9-13.
    • Hong, S.G., Greenspan, E., 2005. Use of minor actinides for reduced power ENHS reactor core design. In: Proceedings of GLOBAL'05, Tsukuba, Japan, October 9-13.
  • 9
    • 0027206934 scopus 로고    scopus 로고
    • Hattori, S., Minato, A., 1993. Current status of 4S plant design. In: Proceedings of the Second ASME-JSME International Conference on Nuclear Engineering: ICONE-2, CA, March 21-24.
    • Hattori, S., Minato, A., 1993. Current status of 4S plant design. In: Proceedings of the Second ASME-JSME International Conference on Nuclear Engineering: ICONE-2, CA, March 21-24.
  • 12
    • 33244455918 scopus 로고    scopus 로고
    • Alternative ENHS core design using stepped geometry core
    • (Washington, DC)
    • Okawa T., and Greenspan E. Alternative ENHS core design using stepped geometry core. Transactions of the American Nuclear Society 91 (November 2004) (Washington, DC)
    • (2004) Transactions of the American Nuclear Society , vol.91
    • Okawa, T.1    Greenspan, E.2
  • 14
    • 22344444177 scopus 로고    scopus 로고
    • Nuclear design of the SAFE-400 space fission reactor
    • Poston D.I. Nuclear design of the SAFE-400 space fission reactor. Nuclear News (December 2002)
    • (2002) Nuclear News
    • Poston, D.I.1
  • 15
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    • Sieniki, J.J., Moisseytsev, A.V., 2005. SSTAR lead-cooled, small modular fast reactor for deployment at remote sites - system thermal hydraulic development. In: Proc. of ICAPP'05, Seoul, Korea, May 15-19.
    • Sieniki, J.J., Moisseytsev, A.V., 2005. SSTAR lead-cooled, small modular fast reactor for deployment at remote sites - system thermal hydraulic development. In: Proc. of ICAPP'05, Seoul, Korea, May 15-19.
  • 16
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    • Stewart, J.S., Lamont, A.D., Rothwell, G.S, Smith, C.F., Greenspan, E., Brown, N., Barak, A., March 1, 2002. An economic analysis of generation iv small modular reactors. Lawrence Livermore National Laboratory Report UCRL-ID-148437.
    • Stewart, J.S., Lamont, A.D., Rothwell, G.S, Smith, C.F., Greenspan, E., Brown, N., Barak, A., March 1, 2002. An economic analysis of generation iv small modular reactors. Lawrence Livermore National Laboratory Report UCRL-ID-148437.
  • 17
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    • Susplugas, A., Greenspan, E., 2005. Implementation of the ENHS thermal hydraulic optimization code for recent ENHS design improvements. UCBNE Internal Report UCB-NE-5104.
    • Susplugas, A., Greenspan, E., 2005. Implementation of the ENHS thermal hydraulic optimization code for recent ENHS design improvements. UCBNE Internal Report UCB-NE-5104.
  • 18
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    • Susplugas, A., Greenspan, E., November 2006. ENHS reactor power level enhancement possibilities. In: Proceedings of the Second COE-INES International Symposium on Innovative Nuclear Energy Systems, INES-2, Yokohama, Japan, 26-30.
    • Susplugas, A., Greenspan, E., November 2006. ENHS reactor power level enhancement possibilities. In: Proceedings of the Second COE-INES International Symposium on Innovative Nuclear Energy Systems, INES-2, Yokohama, Japan, 26-30.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.