메뉴 건너뛰기




Volumn 136, Issue 3, 2001, Pages 261-277

Preliminary FRAPCON-3th steady-state fuel analysis of ThO2 and UO2 fuel mixtures

Author keywords

FRAPCON; Thermal conductivity; Thorium

Indexed keywords

COMPUTER SIMULATION; EVALUATION; FUEL ECONOMY; LIGHT WATER REACTORS; PERFORMANCE; THERMAL CONDUCTIVITY OF SOLIDS; THORIA; URANIUM COMPOUNDS;

EID: 0035578005     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT01-A3244     Document Type: Article
Times cited : (21)

References (11)
  • 4
    • 0004148330 scopus 로고    scopus 로고
    • Development of material property correlations for analysis of mixed 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
    • (2000)
    • Loewen, E.P.1    MacDonald, P.E.2    Hohorst, J.K.3    Sharpe, J.P.4    Siefken, L.J.5
  • 5
    • 0003632278 scopus 로고
    • Thorium dioxide: Properties and nuclear applications
    • DOE/NE-0060, U.S. Department of Energy, Naval Reactors Office
    • (1984)
    • Belle, J.1    Berman, R.M.2
  • 6
    • 0009921739 scopus 로고    scopus 로고
    • FRAPCON-3: A computer code for the calculation of steady-state thermal-mechanical behavior of oxide fuel rods for high burnup
    • PNNL-11513, NUREG/CR-6534, Pacific Northwest National Laboratory, U.S. Nuclear Regulatory Commission
    • (1997)
    • Berna, G.A.1    Beyer, C.E.2    Davis, K.L.3    Lanning, D.D.4
  • 9
    • 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
    • (2000)
    • Yuan, Y.1    Monnier, P.2    Rim, C.S.3    Kazimi, M.A.4
  • 11
    • 0006979990 scopus 로고    scopus 로고
    • NUREG/CR-11513, U.S. Nuclear Regulatory Commission
    • (1997)
    • Lanning, D.D.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.