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Volumn 36, Issue 11, 1999, Pages 996-1008

Advanced nodal methods of the few-group BWR core simulator nereus

Author keywords

Accuracy; Analytic polynomial; BWR type reactors; Control blade history; Depletion model; Discontinuity factors; Few group; Intranodal burnup distribution; Nodal diffusion; Reactor cores; Simulators; Spectral history

Indexed keywords

BOILING WATER REACTORS; DIFFUSION; FINITE DIFFERENCE METHOD; HEAT FLUX; ITERATIVE METHODS; MATHEMATICAL MODELS; NUCLEAR FUELS; NUCLEAR REACTOR SIMULATORS; POLYNOMIALS;

EID: 0033319158     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1999.9726292     Document Type: Article
Times cited : (12)

References (17)
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  • 4
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  • 9
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    • Sitaraman, S., Rahnema, F.: Proc. Joint Int. Conf. on Mathematical Methods and Supercomputing in Nuclear Applications, Karlsruhe, p. 222 (1993).
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    • Sitaraman, S.1    Rahnema, F.2
  • 10
    • 0343080969 scopus 로고    scopus 로고
    • Advances in Nuclear Fuel Management II, Myrtle Beach, SC
    • Borresen, S., Patino, N. E.: Proc. Topical. Mtg. Advances in Nuclear Fuel Management II, Myrtle Beach, SC, p. 5-39 (1997).
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    • Borresen, S.1    Patino, N.E.2
  • 11
    • 0342774607 scopus 로고
    • Preprint 1993 Fall Mtg. Of At
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    • Naka, T.1    Yamamoto, Y.2    Yamamoto, M.3
  • 12
    • 0003438213 scopus 로고
    • An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations
    • MIT, Cambridge, MA
    • Smith, K.: An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations, Engineers Thesis, Dept. Nucl. Eng., MIT, Cambridge, MA, (1979).
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    • Advances in Mathematics, Computation, and Reactor Physics, Pittsburgh, PA
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    • (1991) Proc. Int. Topical. Mtg , vol.10 , Issue.2 , pp. 1-2
    • Yamamoto, M.1    Umano, T.2
  • 15
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    • (1985) NEDO-30130-A


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.