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Volumn 137, Issue 2, 2002, Pages 97-110

Reactivity, isotopic, and thermal steady-state analysis of homogeneous thoria-urania fuel

Author keywords

[No Author keywords available]

Indexed keywords

CALCULATIONS; COMBUSTION; DISCHARGE (FLUID MECHANICS); HEAT TRANSFER; MATHEMATICAL MODELS; MONTE CARLO METHODS; NEUTRONS; PERFORMANCE; THERMAL CONDUCTIVITY; THERMAL EXPANSION; THORIA; URANIUM COMPOUNDS;

EID: 0036468602     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT02-A3260     Document Type: Article
Times cited : (5)

References (14)
  • 4
    • 0003632278 scopus 로고
    • Thorium dioxide: Properties and nuclear applications
    • DOE/NE-0060, DE85 006670, U.S. Department of Energy, Naval Reactors Office
    • (1984)
    • Belle, J.1    Berman, R.M.2
  • 5
    • 0008269676 scopus 로고    scopus 로고
    • SCDAP/RELAPS/MOD 3.2 code manual: MATPRO-a library of materials properties for light water reactor accident analysis
    • SCDAP/RELAP5 DEVELOPMENT TEAM; NUREG/CR-6150; Rev. 1, INEEL-96/0422, Idaho National Engineering and Environmental Laboratory
    • (1996) , vol.4
  • 6
    • 0004148330 scopus 로고    scopus 로고
    • Development of material property correlations for analysis of mix thoria-urania fuel performance in light water reactors and augmentation of the FRAPCON-3 computer code
    • INEEL/EXT-2000-00275, Idaho National Engineering and Environmental Laboratory (Aug.)
    • (2000)
    • Loewen, E.P.1    MacDonald, P.E.2    Hohorst, J.K.3    Sharpe, J.P.4    Siefken, L.5
  • 7
    • 0003520671 scopus 로고    scopus 로고
    • Fission gas release modeling for thoria-urania fuels: A preliminary investigation
    • MIT-NFC-TR-022, Massachusetts Institute of Technology, Department of Nuclear Engineering (Sep.)
    • (2000)
    • Yuan, Y.1    Monnier, P.2    Rim, C.S.3    Kazimi, M.S.4
  • 9
    • 0003395844 scopus 로고    scopus 로고
    • "MCNP-a general Monte Carlo n-particle transport code," version 4B
    • J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory
    • (1997)
  • 10
    • 0003662791 scopus 로고
    • "A user's manual for the ORIGEN2 computer code," version 2.1
    • Oak Ridge National Laboratory
    • (1980)
    • Croff, A.G.1
  • 14
    • 4244053302 scopus 로고
    • Method for calculating the fractional release of volatile fission products from oxide fuel
    • ANSI/ANS-5.4-1982, American Nuclear Society; (a historical standard)
    • (1982)


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.