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Volumn 151, Issue 2, 2005, Pages 133-158

Use of sensitivity and uncertainty analysis in the design of reactor physics and criticality benchmark experiments for advanced nuclear fuel

Author keywords

Experiment design; Highly enriched fuel; Sensitivity and uncertainty analysis

Indexed keywords

BOILING WATER REACTORS; CODES (STANDARDS); DESIGN; PRESSURIZED WATER REACTORS; REACTOR CORES; SENSITIVITY ANALYSIS; URANIUM DIOXIDE;

EID: 22944463785     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT05-A3639     Document Type: Article
Times cited : (8)

References (9)
  • 1
    • 22944492569 scopus 로고
    • "Specification for Uranium Dioxide Pellets"
    • Spec. No. 41-1001, Allis-Chalmers Manufacturing Company, Atomic Energy Division
    • "Specification for Uranium Dioxide Pellets," Spec. No. 41-1001, Allis-Chalmers Manufacturing Company, Atomic Energy Division (1965).
    • (1965)
  • 2
    • 22944490367 scopus 로고    scopus 로고
    • "Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel"
    • SAND2004-0912, Sandia National Laboratories
    • G. A. HARMS, P. H. HEMMICK, J. T. FORD, S. A.WALKER, D. T. BERRY, and P. S. PICKARD, "Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel," SAND2004-0912, Sandia National Laboratories (2004).
    • (2004)
    • Harms, G.A.1    Hemmick, P.H.2    Ford, J.T.3    Walker, S.A.4    Berry, D.T.5    Pickard, P.S.6
  • 4
    • 1842588312 scopus 로고    scopus 로고
    • "Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques"
    • B. T. REARDEN, "Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques," Nucl. Sci. Eng., 146, 367 (2004).
    • (2004) Nucl. Sci. Eng. , vol.146 , pp. 367
    • Rearden, B.T.1
  • 5
    • 0003894050 scopus 로고    scopus 로고
    • "SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation"
    • NUREG/CR-0200, Rev. 7 (ORNL/NUREG/CSD-2/V1/R7), Oak Ridge National Laboratory (June)
    • "SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation," NUREG/CR-0200, Rev. 7 (ORNL /NUREG/ CSD-2/V1/R7), Oak Ridge National Laboratory (June 2004).
    • (2004)
  • 6
    • 0142149070 scopus 로고    scopus 로고
    • "Use of Sensitivity and Uncertainty Analysis to Select Benchmark Experiments for the Validation of Computer Codes and Data"
    • K. R. ELAM and B. T. REARDEN, "Use of Sensitivity and Uncertainty Analysis to Select Benchmark Experiments for the Validation of Computer Codes and Data," Nucl. Sci. Eng., 145, 196 (2003).
    • (2003) Nucl. Sci. Eng. , vol.145 , pp. 196
    • Elam, K.R.1    Rearden, B.T.2
  • 7
    • 0012308015 scopus 로고    scopus 로고
    • "International Handbook of Evaluated Criticality Safety Benchmark Experiments"
    • Nuclear Energy Agency Nuclear Science Committee of the Organization for Economic Co-operation and Development, NEA/NSC/DOC(95)03, Nuclear Energy Agency
    • "International Handbook of Evaluated Criticality Safety Benchmark Experiments," Nuclear Energy Agency Nuclear Science Committee of the Organization for Economic Co-operation and Development, NEA/NSC/ DOC(95)03, Nuclear Energy Agency (2003).
    • (2003)
  • 8
    • 0038717027 scopus 로고    scopus 로고
    • "Extended Interpretation of Sensitivity Data for Benchmark Areas of Applicability"
    • S. GOLUOGLU, C. M. HOPPER, and B. T. REARDEN, "Extended Interpretation of Sensitivity Data for Benchmark Areas of Applicability," Trans. Am. Nucl. Soc., 88, 77 (2003).
    • (2003) Trans. Am. Nucl. Soc. , vol.88 , pp. 77
    • Goluoglu, S.1    Hopper, C.M.2    Rearden, B.T.3
  • 9
    • 0142252103 scopus 로고    scopus 로고
    • "PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices"
    • ORNL/TM-1999/235 (NUREG/CR-6650), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory
    • M. E. DUNN, "PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices," ORNL/TM-1999/235 (NUREG /CR-6650), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (2000).
    • (2000)
    • Dunn, M.E.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.