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Volumn 238, Issue 12, 2008, Pages 3561-3578

Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENTS; BUILDINGS; LOSS OF COOLANT ACCIDENTS; NUCLEAR REACTOR ACCIDENTS; UNCERTAINTY ANALYSIS;

EID: 55049132746     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2008.06.004     Document Type: Article
Times cited : (64)

References (25)
  • 1
    • 55049128029 scopus 로고    scopus 로고
    • Bayless, P.D., Divine, J.M., 1982. Experiment data report for LOFT Large Break Loss Of Coolant Experiment L2-5. NUREG/CR-2826, EGG-2210.
    • Bayless, P.D., Divine, J.M., 1982. Experiment data report for LOFT Large Break Loss Of Coolant Experiment L2-5. NUREG/CR-2826, EGG-2210.
  • 2
    • 55049099023 scopus 로고    scopus 로고
    • Bolado, R., Devictor, N., 2005. The use of Expert Judgement in Decision Making. Organised by European Commission organised by European Commission, DG Joint Research Center, Institute for Energy and Commissariat à l'Energie Atomique, Aix-en-Provence, France, 21-23 June 2005.
    • Bolado, R., Devictor, N., 2005. The use of Expert Judgement in Decision Making. Organised by European Commission organised by European Commission, DG Joint Research Center, Institute for Energy and Commissariat à l'Energie Atomique, Aix-en-Provence, France, 21-23 June 2005.
  • 3
    • 0041555371 scopus 로고
    • Scaling of the accuracy of RELAP5/Mod 2 Code
    • Bovalini R., and D'Auria F. Scaling of the accuracy of RELAP5/Mod 2 Code. Nuclear Engineering and Design 139 2 (1993) 187-204
    • (1993) Nuclear Engineering and Design , vol.139 , Issue.2 , pp. 187-204
    • Bovalini, R.1    D'Auria, F.2
  • 5
    • 55049125285 scopus 로고    scopus 로고
    • CSNI: Committee on the Safety of Nuclear Installations (NEA, OECD), 1998. Report on the Uncertainty Methods Study. NEA/CSNI R(97) 35, vols. I and II.
    • CSNI: Committee on the Safety of Nuclear Installations (NEA, OECD), 1998. Report on the Uncertainty Methods Study. NEA/CSNI R(97) 35, vols. I and II.
  • 6
    • 55049127389 scopus 로고    scopus 로고
    • CSNI: Committee on the Safety of Nuclear Installations (NEA, OECD), 2007. BEMUSE Phase III Report. NEA/CSNI R(2007) 4, October 2007.
    • CSNI: Committee on the Safety of Nuclear Installations (NEA, OECD), 2007. BEMUSE Phase III Report. NEA/CSNI R(2007) 4, October 2007.
  • 9
    • 0029172648 scopus 로고
    • Outline of the uncertainty methodology based on accuracy extrapolation (UMAE)
    • D'Auria F., Debrecin N., and Galassi G.M. Outline of the uncertainty methodology based on accuracy extrapolation (UMAE). Journal of Nuclear Technology 109 1 (1995) 21-38
    • (1995) Journal of Nuclear Technology , vol.109 , Issue.1 , pp. 21-38
    • D'Auria, F.1    Debrecin, N.2    Galassi, G.M.3
  • 10
    • 0034249270 scopus 로고    scopus 로고
    • Development of code with capability of internal assessment of uncertainty
    • D'Auria F., and Giannotti W. Development of code with capability of internal assessment of uncertainty. Journal of Nuclear Technology 131 1 (2000) 159-196
    • (2000) Journal of Nuclear Technology , vol.131 , Issue.1 , pp. 159-196
    • D'Auria, F.1    Giannotti, W.2
  • 11
    • 0028596709 scopus 로고
    • Uncertainty and sensitivity analysis of a post-experiment calculation in thermals hydraulics
    • Glaeser H., Hofer E., Kloos M., and Skorek T. Uncertainty and sensitivity analysis of a post-experiment calculation in thermals hydraulics. Reliability Engineering and System Safety 45 (1994) 19-33
    • (1994) Reliability Engineering and System Safety , vol.45 , pp. 19-33
    • Glaeser, H.1    Hofer, E.2    Kloos, M.3    Skorek, T.4
  • 12
    • 55049111569 scopus 로고    scopus 로고
    • Hofer, E. et al., 1985 Uncertainty and sensitivity analysis of accident consequence submodels. In: Proc. Int. ANS/ENS Topical Mtg on Probabilistic Safety Methods and Applications, vol. 2, San Francisco, CA. Electric Power Research Institute, Palo Alto, CA, p. 130.
    • Hofer, E. et al., 1985 Uncertainty and sensitivity analysis of accident consequence submodels. In: Proc. Int. ANS/ENS Topical Mtg on Probabilistic Safety Methods and Applications, vol. 2, San Francisco, CA. Electric Power Research Institute, Palo Alto, CA, p. 130.
  • 13
    • 0030121081 scopus 로고    scopus 로고
    • Importance measures in global sensitivity analysis of nonlinear models
    • Homma T., and Saltelli A. Importance measures in global sensitivity analysis of nonlinear models. Reliability Engineering and System Safety 52 (1996) 1-17
    • (1996) Reliability Engineering and System Safety , vol.52 , pp. 1-17
    • Homma, T.1    Saltelli, A.2
  • 14
    • 55049100313 scopus 로고    scopus 로고
    • ISL: Information Systems Laboratories, 2001. RELAP5/MOD3.3 Code Manual, vol. 1-8, NUREG/CR-5535/Rev. 1.
    • ISL: Information Systems Laboratories, 2001. RELAP5/MOD3.3 Code Manual, vol. 1-8, NUREG/CR-5535/Rev. 1.
  • 16
    • 34548614979 scopus 로고
    • Quantifying reactor safety margins. Part 4: uncertainty evaluation of LBLOCA analysis based on TRAC-PF1/MOD 1
    • Lellouche G.S., Levy S., et al. Quantifying reactor safety margins. Part 4: uncertainty evaluation of LBLOCA analysis based on TRAC-PF1/MOD 1. Nuclear Engineering and Design 119 (1990) 67-95
    • (1990) Nuclear Engineering and Design , vol.119 , pp. 67-95
    • Lellouche, G.S.1    Levy, S.2
  • 17
    • 55049139003 scopus 로고    scopus 로고
    • Reeder, D.L., 1978. LOFT systems and test description (5.5 ft Nuclear core 1 LOCES). NUREG-CR-0247 TREE-1208.
    • Reeder, D.L., 1978. LOFT systems and test description (5.5 ft Nuclear core 1 LOCES). NUREG-CR-0247 TREE-1208.
  • 18
    • 55049103048 scopus 로고    scopus 로고
    • Robinson, H.C., 1976. LOFT systems and test description (Loss-of-coolant experiment using a core simulator). TREE-NUREG-1019.
    • Robinson, H.C., 1976. LOFT systems and test description (Loss-of-coolant experiment using a core simulator). TREE-NUREG-1019.
  • 19
    • 55049087934 scopus 로고    scopus 로고
    • Russel, M.M., 1977. Loft Fuel Modules Design, Characterization, and Fabrication Program. TREE-NUREG-1131.
    • Russel, M.M., 1977. Loft Fuel Modules Design, Characterization, and Fabrication Program. TREE-NUREG-1131.
  • 22
    • 0002765765 scopus 로고
    • Determination of sample sizes for setting tolerance limits. Lothar Sachs
    • Springler-Verlag pp. 91-96
    • Wilks S.S. Determination of sample sizes for setting tolerance limits. Lothar Sachs. Applied Statistics. 2nd edition (1984), Springler-Verlag pp. 91-96
    • (1984) Applied Statistics. 2nd edition
    • Wilks, S.S.1
  • 23
    • 38249018472 scopus 로고
    • Quantifying reactor safety margins. Part 2: Characterization of important contributors to uncertainty
    • Wilson G.E., et al. Quantifying reactor safety margins. Part 2: Characterization of important contributors to uncertainty. Nuclear Engineering and Design 119 (1990) 17-31
    • (1990) Nuclear Engineering and Design , vol.119 , pp. 17-31
    • Wilson, G.E.1
  • 24
    • 55049130214 scopus 로고    scopus 로고
    • WGAMA: Working Group on the Analysis and Management of Accidents (CSNI, NEA, OECD), 2003. Best-Estimate Methods (Including Uncertainty Methods and Evaluation) Qualification and Application. First Meeting of the Programme Committee. NEA/SEN/SIN/AMA(2003)8.
    • WGAMA: Working Group on the Analysis and Management of Accidents (CSNI, NEA, OECD), 2003. Best-Estimate Methods (Including Uncertainty Methods and Evaluation) Qualification and Application. First Meeting of the Programme Committee. NEA/SEN/SIN/AMA(2003)8.
  • 25
    • 38249018174 scopus 로고
    • Quantifying reactor safety margins. Part 3: assessment and ranging of parameters
    • Wulff W., et al. Quantifying reactor safety margins. Part 3: assessment and ranging of parameters. Nuclear Engineering and Design 119 (1990) 33-65
    • (1990) Nuclear Engineering and Design , vol.119 , pp. 33-65
    • Wulff, W.1


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