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Volumn 239, Issue 8, 2009, Pages 1544-1559

Steady state thermal-hydraulic analysis of hydride-fueled grid-supported BWRs

Author keywords

[No Author keywords available]

Indexed keywords

CENTERLINE; CORE BEHAVIORS; CORE VALUES; FLOW INDUCED VIBRATIONS; FUEL RODS; HEAT TRANSFER AREA; HYDRIDE FUEL; HYDRODYNAMIC STABILITY; INDEPENDENT ANALYSIS; MINIMUM CRITICAL POWER RATIO; NEUTRONIC; NEUTRONIC STUDIES; NEUTRONICS; OUTER TEMPERATURE; OXIDE FUEL CORES; OXIDE FUELS; P-VALUE; PIN POWER DISTRIBUTION; POWER DENSITIES; POWER GAINS; POWER LIMITING; SAFETY REQUIREMENTS; STEADY STATE; THERMAL HYDRAULICS; THERMAL-HYDRAULIC ANALYSIS; THERMAL-HYDRAULIC PERFORMANCE; WATER GAPS; WATER RODS;

EID: 67349169534     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.12.029     Document Type: Article
Times cited : (4)

References (29)
  • 2
    • 67349274892 scopus 로고    scopus 로고
    • EPRI-NP-2609, 1982. Parametric Study of CHF Data, 2: A generalized Subchannel CHF Correlation for PWR and BWR Fuel Assemblies, Electric Power Research Institute, Palo Alto, California, Prepared by Heat Transfer Research Facility, Department of Chemical Engineering, Columbia University, New York.
    • EPRI-NP-2609, 1982. Parametric Study of CHF Data, Volume 2: A generalized Subchannel CHF Correlation for PWR and BWR Fuel Assemblies", Electric Power Research Institute, Palo Alto, California, Prepared by Heat Transfer Research Facility, Department of Chemical Engineering, Columbia University, New York.
  • 3
    • 67349219319 scopus 로고    scopus 로고
    • ESBWR Design Control Document, 2007. Tier 2, Chapter 4 Reactor. 26A6642AP. Revision 4. Available at NRC electronic library, ADAMS No. ML072900630.
    • ESBWR Design Control Document, 2007. Tier 2, Chapter 4 "Reactor". 26A6642AP. Revision 4. Available at NRC electronic library, ADAMS No. ML072900630.
  • 4
    • 67349255168 scopus 로고    scopus 로고
    • 2004, GNF, to Greenspan, E, University of California Berkeley, Personal Communication. November 2004
    • Fawcett, R.M., 2004. (GNF), to Greenspan, E. (University of California Berkeley), Personal Communication. November 2004.
    • Fawcett, R.M.1
  • 8
    • 67349140858 scopus 로고    scopus 로고
    • Proposed correlations for cladding thickness and fuel-cladding gap for UO2 and U-ZrH fuel in BWRs
    • NERI02-189-WEC-07
    • Garkisch, H.D., Petrovic, B., 2004. Proposed correlations for cladding thickness and fuel-cladding gap for UO2 and U-ZrH fuel in BWRs. Research Group Internal Report, NERI02-189-WEC-07.
    • (2004) Research Group Internal Report
    • Garkisch, H.D.1    Petrovic, B.2
  • 9
    • 67349101142 scopus 로고
    • US Patent 5,349,618. BWR fuel assembly having oxide and hydride fuel
    • Greenspan, E., 1994. US Patent 5,349,618. BWR fuel assembly having oxide and hydride fuel.
    • (1994)
    • Greenspan, E.1
  • 11
    • 67349114764 scopus 로고    scopus 로고
    • Hench, J.E., Gillis, J.C., 1981. Correlation of Critical Heat Flux Data for Application to Boiling Water Reactor Conditions. EPRI NP-1898.
    • Hench, J.E., Gillis, J.C., 1981. Correlation of Critical Heat Flux Data for Application to Boiling Water Reactor Conditions. EPRI NP-1898.
  • 12
    • 67349198002 scopus 로고    scopus 로고
    • IAEA-TECDOC-1391, 2004. Status of Advanced Light Water Reactor Design 2004.
    • IAEA-TECDOC-1391, 2004. Status of Advanced Light Water Reactor Design 2004.
  • 15
    • 30844446150 scopus 로고
    • Zirconium hydride fuel element performance characteristics
    • Atomics International Division, Canoga Park, CA, USA
    • Lillie A.F., McClelland D.T., Roberts W.J., and Walter J.H. Zirconium hydride fuel element performance characteristics. Proceedings of the AIAEC13084. Atomics International Division, Canoga Park, CA, USA (1973)
    • (1973) Proceedings of the AIAEC13084
    • Lillie, A.F.1    McClelland, D.T.2    Roberts, W.J.3    Walter, J.H.4
  • 16
    • 67349256304 scopus 로고    scopus 로고
    • Lungmen Power Station Units 1&2, 1999. Preliminary Safety Analysis Report (PSAR). Available online at: http://japan.nonukesasiaforum.org/lungmen/.
    • Lungmen Power Station Units 1&2, 1999. Preliminary Safety Analysis Report (PSAR). Available online at: http://japan.nonukesasiaforum.org/lungmen/.
  • 18
    • 0001921715 scopus 로고
    • Coupled thermal-hydraulic-neutronic instabilities in boiling water nuclear reactors: a review of the state of the art
    • March-Leuba J., and Rey J.M. Coupled thermal-hydraulic-neutronic instabilities in boiling water nuclear reactors: a review of the state of the art. Nuclear Engineering and Design 146 1993 (1993) 97-111
    • (1993) Nuclear Engineering and Design , vol.146 , Issue.1993 , pp. 97-111
    • March-Leuba, J.1    Rey, J.M.2
  • 19
    • 67349230779 scopus 로고    scopus 로고
    • Nine Mile Point Unit 2, 2004. Updated Safety Analysis Report (USAR), Rev.16.
    • Nine Mile Point Unit 2, 2004. Updated Safety Analysis Report (USAR), Rev.16.
  • 20
    • 67349083476 scopus 로고    scopus 로고
    • NRC 10CFR50.46, 2007. US Nuclear Regulatory Commission Regulations, Title 10 Code of Federal Regulations, Part 50-Domestic Licensing of Production and Utilization Facilities. August 28, 2007
    • NRC 10CFR50.46, 2007. US Nuclear Regulatory Commission Regulations, Title 10 Code of Federal Regulations, Part 50-Domestic Licensing of Production and Utilization Facilities. August 28, 2007.
  • 23
    • 0020175685 scopus 로고
    • On the vibrational behavior of pressurized water reactor fuel rods
    • Preumont A. On the vibrational behavior of pressurized water reactor fuel rods. Nuclear Technology 58 (1982) 483-491
    • (1982) Nuclear Technology , vol.58 , pp. 483-491
    • Preumont, A.1
  • 24
    • 67349203797 scopus 로고    scopus 로고
    • Shiralkar, B., 2006. TRACG Application for ESBWR Stability. ACRS Thermal-Hydraulic Phenomena Subcommittee. Available at NRC electronic library, ADAMS No. ML060340089.
    • Shiralkar, B., 2006. TRACG Application for ESBWR Stability. ACRS Thermal-Hydraulic Phenomena Subcommittee. Available at NRC electronic library, ADAMS No. ML060340089.
  • 25
    • 0019551250 scopus 로고
    • x alloy: its properties and use in TRIGA fuel
    • x alloy: its properties and use in TRIGA fuel. Nuclear Engineering and Design 64 1981 (1981) 403-422
    • (1981) Nuclear Engineering and Design , vol.64 , Issue.1981 , pp. 403-422
    • Simnad, M.T.1
  • 26
    • 0005495871 scopus 로고
    • VIPRE-01: A Thermal-Hydraulic Code for Reactor Cores
    • EPRI NP-2511-CCM. Electric Power Research Institute
    • Stewart, C.W., et al., 1989. VIPRE-01: A Thermal-Hydraulic Code for Reactor Cores, Volume 2: User's Manual. EPRI NP-2511-CCM. Electric Power Research Institute.
    • (1989) User's Manual , vol.2
    • Stewart, C.W.1
  • 27
    • 67349207305 scopus 로고
    • Nuclear Systems I, Thermal Hydraulic Fundamentals, Taylor & Francis
    • Todreas, N.E., Kazimi, M.S., 1993. Nuclear Systems I, Thermal Hydraulic Fundamentals, Taylor & Francis, 2nd printing, pp. 305-306.
    • (1993) 2nd printing , pp. 305-306
    • Todreas, N.E.1    Kazimi, M.S.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.