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Volumn 145, Issue 1, 2004, Pages 11-17

A simple and efficient control rod cusping model for three-dimensional pin-by-pin core calculations

Author keywords

Control rod cusping problem; Inverse spectral index weighting; Pin by pin core calculation

Indexed keywords

BOUNDARY VALUE PROBLEMS; COMPUTATIONAL METHODS; DISCRETE TIME CONTROL SYSTEMS; HEAT FLUX; MATHEMATICAL MODELS; NUCLEAR REACTORS; SPECTRUM ANALYZERS;

EID: 0742290090     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT145-11     Document Type: Article
Times cited : (33)

References (12)
  • 1
    • 0022902897 scopus 로고
    • Progress in Nodal Methods for the Solution of the Neutron Diffusion and Transport Equations
    • R. D. LAWRENCE, "Progress in Nodal Methods for the Solution of the Neutron Diffusion and Transport Equations," Prog. Nucl. Energy, 17, 271 (1986).
    • (1986) Prog. Nucl. Energy , vol.17 , pp. 271
    • Lawrence, R.D.1
  • 2
    • 0022860977 scopus 로고
    • Assembly Homogenization Techniques for Light Water Reactor Analysis
    • K. S. SMITH, "Assembly Homogenization Techniques for Light Water Reactor Analysis," Prog. Nucl. Energy, 17, 303 (1986).
    • (1986) Prog. Nucl. Energy , vol.17 , pp. 303
    • Smith, K.S.1
  • 5
  • 6
    • 0006451754 scopus 로고
    • A Bilinear Weighting Method for the Control Rod Cusping Problem in Nodal Methods
    • Y. H. KIM and N. Z. CHO, "A Bilinear Weighting Method for the Control Rod Cusping Problem in Nodal Methods," J. Korean Nucl. Soc., 22, 238 (1990).
    • (1990) J. Korean Nucl. Soc. , vol.22 , pp. 238
    • Kim, Y.H.1    Cho, N.Z.2
  • 8
    • 84881510256 scopus 로고    scopus 로고
    • SCOPE2: Object-Oriented Parallel Code for Multi-Group Diffusion/ Transport Calculations in Three-Dimensional Fine-Mesh Reactor Core Geometry
    • Seoul, Korea, October 7-10, 12A-01 (2002) (CD-ROM)
    • M. TATSUMI and A. YAMAMOTO, "SCOPE2: Object-Oriented Parallel Code for Multi-Group Diffusion/Transport Calculations in Three-Dimensional Fine-Mesh Reactor Core Geometry," Proc. Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, Seoul, Korea, October 7-10, 2002, 12A-01 (2002) (CD-ROM).
    • (2002) Proc. Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-performance Computing
    • Tatsumi, M.1    Yamamoto, A.2
  • 9
    • 0042929219 scopus 로고    scopus 로고
    • PWR Core Calculations by the Multigroup Nodal-Transport Method in 3-D Pin-by-Pin Geometry
    • M. TATSUMI and A. YAMAMOTO, "PWR Core Calculations by the Multigroup Nodal-Transport Method in 3-D Pin-by-Pin Geometry," Trans. Am. Nucl. Soc., 87, 232 (2002).
    • (2002) Trans. Am. Nucl. Soc. , vol.87 , pp. 232
    • Tatsumi, M.1    Yamamoto, A.2
  • 10
    • 0043201031 scopus 로고    scopus 로고
    • Advanced PWR Core Calculation Based on Multi-Group Nodal-Transport Method in Three-Dimensional Pin-by-Pin Geometry
    • M. TATSUMI and A. YAMAMOTO, "Advanced PWR Core Calculation Based on Multi-Group Nodal-Transport Method in Three-Dimensional Pin-by-Pin Geometry," J. Nucl. Sci. Technol., 40, 376 (2003).
    • (2003) J. Nucl. Sci. Technol. , vol.40 , pp. 376
    • Tatsumi, M.1    Yamamoto, A.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.