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Volumn 142, Issue 3, 2002, Pages 258-269

Simulation of mixed-oxide and low-enriched uranium fuel burnup in a pressurized water reactor and validation against destructive analysis results

Author keywords

[No Author keywords available]

Indexed keywords

CESIUM; COMPUTER SIMULATION; FISSION REACTIONS; IRRADIATION; ISOTOPES; MIXED OXIDE FUELS; NEODYMIUM; NUCLEAR FUELS; PRESSURIZED WATER REACTORS; SAMARIUM; URANIUM;

EID: 0036862944     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE02-A2306     Document Type: Article
Times cited : (12)

References (11)
  • 1
    • 0012060971 scopus 로고    scopus 로고
    • Characteristics of spent fuel from plutonium disposition reactors, vol. 3: A westinghouse pressurized-water reactor design
    • ORNL/TM-13170, Oak Ridge National Laboratory (July)
    • B. D. MURPHY, "Characteristics of Spent Fuel from Plutonium Disposition Reactors, Vol. 3: A Westinghouse Pressurized-Water Reactor Design," ORNL/TM-13170, Oak Ridge National Laboratory (July 1997).
    • (1997)
    • Murphy, B.D.1
  • 2
    • 0003649814 scopus 로고    scopus 로고
    • Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages
    • ORNL/TM-12973, Oak Ridge National Laboratory (May)
    • M. D. DeHART, "Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages," ORNL/TM-12973, Oak Ridge National Laboratory (May 1996).
    • (1996)
    • DeHart, M.D.1
  • 4
    • 0012086752 scopus 로고    scopus 로고
    • Standard test method for atom percent fission in uranium and plutonium fuel (neodymium-148 method)
    • E321, American Society for Testing Materials
    • "Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)," Annual Book of Standards, Vol. 12.01, E321, American Society for Testing Materials (1996).
    • (1996) Annual Book of Standards , vol.12 , Issue.1
  • 5
    • 4243253849 scopus 로고    scopus 로고
    • SCALE: A modular code system for performing standardized computer analyses for licensing evaluation
    • Oak Ridge National Laboratory (May); see also CCC-545, Radiation Safety Information Computational Center, Oak Ridge National Laboratory
    • "SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation," NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III, Oak Ridge National Laboratory (May 2000); see also CCC-545, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
    • (2000) NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6) , vol.1-3
  • 6
    • 0004094009 scopus 로고    scopus 로고
    • Neutronics benchmark for the quad cities-1 (cycle 2) mixed-oxide assembly irradiation
    • ORNL/TM-13567, Oak Ridge National Laboratory (Apr.)
    • S. E. FISHER AND F. C. DIFILIPPO, "Neutronics Benchmark for the Quad Cities-1 (Cycle 2) Mixed-Oxide Assembly Irradiation," ORNL/TM-13567, Oak Ridge National Laboratory (Apr. 1998).
    • (1998)
    • Fisher, S.E.1    Difilippo, F.C.2
  • 7
    • 0012093105 scopus 로고    scopus 로고
    • Quality assurance calculations to support use of HELIOS version 1.6 for plutonium disposition studies
    • ORNL/TM-2001/50, UT-Battelle, LLC, Oak Ridge National Laboratory (Apr.)
    • C. E. SANDERS AND R. T. PRIMM III, "Quality Assurance Calculations to Support Use of HELIOS Version 1.6 for Plutonium Disposition Studies," ORNL/TM-2001/50, UT-Battelle, LLC, Oak Ridge National Laboratory (Apr. 2001).
    • (2001)
    • Sanders, C.E.1    Primm R.T. III2
  • 8
    • 0012030806 scopus 로고    scopus 로고
    • Oak Ridge National Laboratory, Personal Communication to B. D. MURPHY, Oak Ridge National Laboratory (Apr.)
    • B. T. REARDEN, Oak Ridge National Laboratory, Personal Communication to B. D. MURPHY, Oak Ridge National Laboratory (Apr. 2000).
    • (2000)
    • Rearden, B.T.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.