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Volumn 35, Issue 1, 2008, Pages 37-48

SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies

Author keywords

[No Author keywords available]

Indexed keywords

COOLING; LIGHT WATER REACTORS; THERMAL VARIABLES MEASUREMENT; TIME DOMAIN ANALYSIS;

EID: 36148960061     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2007.05.017     Document Type: Article
Times cited : (19)

References (17)
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    • DeHart, M.D., 1992. A discrete ordinates approximation to the neutron transport equation applied to generalized geometries. Ph.D. Dissertation, Texas A&M University.
  • 2
    • 33847214931 scopus 로고    scopus 로고
    • DeHart, M.D., Ulses, A.P., 2006. Lattice physics capabilities of the SCALE code system using TRITON. In: CD Proceedings of the ANS Topical Meeting on Reactor Physics PHYSOR-2006.
  • 3
    • 33847177267 scopus 로고    scopus 로고
    • Gauld, I.C., 2006. Validation of ORIGEN-S decay heat predictions for LOCA analysis. In: CD Proceedings of the ANS Topical Meeting on Reactor Physics PHYSOR-2006.
  • 4
    • 36148992681 scopus 로고    scopus 로고
    • Gauld, I.C., Ilas, G., Murphy, B.D., Weber, C.F., 2006. Validation of SCALE 5 decay heat predictions for LWR spent nuclear fuel. Technical Report ORNL/TM-2006/13, Oak Ridge National Laboratory.
  • 5
    • 36148953998 scopus 로고    scopus 로고
    • Guttman, I., Wilks, S.S., Hunter, J.S., 1971. Introductory Engineering Statistics, Wiley Series in Probability and Mathematical Statistics - Applied. John Wiley & Sons.
  • 6
    • 36148935694 scopus 로고    scopus 로고
    • Hermann, O.W., Parks, C.V., Renier, J.P., 1994. Technical support for a proposed decay heat guide using SAS2H/ORIGEN-S data. Technical Report NUREG/CR-5625 (ORNL-6698), US Nuclear Regulatory Commission, Oak Ridge National Laboratory.
  • 7
    • 33746220163 scopus 로고    scopus 로고
    • Analysis of decay heat measurements for BWR fuel assemblies
    • Ilas G., and Gauld I.C. Analysis of decay heat measurements for BWR fuel assemblies. ANS Transactions 94 (2006) 385
    • (2006) ANS Transactions , vol.94 , pp. 385
    • Ilas, G.1    Gauld, I.C.2
  • 8
    • 36148983133 scopus 로고    scopus 로고
    • Ilas, G., Gauld, I.C., Difilippo, F.C., Emmett, M.B., 2007. Analysis of experimental data for high burnup PWR spent fuel isotopic validation - Calvert Cliffs, Takahama, and Three Mile Island reactors. Technical Report ORNL/TM-2007/19, Oak Ridge National Laboratory.
  • 9
    • 36148985813 scopus 로고    scopus 로고
    • Murphy, B.D., Gauld, I.C., 2006. Spent fuel decay heat measurements performed at the Swedish central interim storage facility. Technical Report ORNL/TM-2006/18, Oak Ridge National Laboratory.
  • 10
    • 36148961304 scopus 로고    scopus 로고
    • NIST/SEMATECH e-Handbook of Statistical Methods, 2006. http://www.itl.nist.gov/div898/handbook/.
  • 11
    • 36148942930 scopus 로고    scopus 로고
    • O'Donnell, G.M., Scott, H.H., Meyer, R.O., 2001. A new comparative analysis of LWR fuel designs. Technical Report NUREG-1754, US Nuclear Regulatory Commission.
  • 12
    • 36148973263 scopus 로고    scopus 로고
    • Origin, 2004. Graphing and Analysis Software, Version Pro7.5 SR5. OriginLab Corporation.
  • 13
    • 36148977282 scopus 로고    scopus 로고
    • Regulatory Guide 3.54, 1999. Spent fuel heat generation in an independent spent fuel storage installation, Revision 1. US Nuclear Regulatory Commission.
  • 14
    • 36148950215 scopus 로고    scopus 로고
    • RSICC Computer Code Collection, CCC-732, 2006. SCALE: a modular code system for performing standardized computer analyses for licensing evaluations, ORNL/TM-2005/39, Version 5.1. Oak Ridge National Laboratory.
  • 15
    • 36148951839 scopus 로고    scopus 로고
    • SCALE Validation/Benchmark Reports, 2006. http://www.ornl.gov/sci/scale/spentfuel.htm.
  • 16
    • 36148975817 scopus 로고    scopus 로고
    • Schmittroth, F., Neely, G.J., Wootan, D.W., 1980. Uncertainties in decay heat calculations for spent fuel. Technical Report TC-1636, Hanford Engineering Development Laboratory.
  • 17
    • 36148977685 scopus 로고    scopus 로고
    • Wagner, J.C., Parks, C.V., 2002. Parametric study of the effect of burnable poison rods for PWR burnup credit. Technical Report NUREG/CR-6761, ORNL/TM-2000/373, Oak Ridge National Laboratory.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.