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Volumn 100, Issue , 2009, Pages 619-620

Integration of the NESTLE core simulator with SCALE

Author keywords

[No Author keywords available]

Indexed keywords


EID: 72749089684     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (7)

References (6)
  • 1
    • 72749127299 scopus 로고    scopus 로고
    • SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732
    • SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.
  • 2
    • 72749089597 scopus 로고    scopus 로고
    • M. D. DeHart, TRITON: A Two-Dimensional Transport and Depletion Module for Characterization of Spent Nuclear Fuel, ORNL/TM-2005/39, Version 5, I, Book 3, Section T1, November 2006.
    • M. D. DeHart, "TRITON: A Two-Dimensional Transport and Depletion Module for Characterization of Spent Nuclear Fuel," ORNL/TM-2005/39, Version 5, Vol. I, Book 3, Section T1, November 2006.
  • 3
    • 51849100460 scopus 로고
    • Code Abstract - NESTLE: A Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady-State and Transient Problems
    • P. J. Turinsky, R. M. Al-Chalabi, P. Engrand, H. N. Sarsour, F. X. Faure and W. Guo, "Code Abstract - NESTLE: A Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady-State and Transient Problems," Nucl. Sci. & Engr., 120, 72, 1995.
    • (1995) Nucl. Sci. & Engr , vol.120 , pp. 72
    • Turinsky, P.J.1    Al-Chalabi, R.M.2    Engrand, P.3    Sarsour, H.N.4    Faure, F.X.5    Guo, W.6
  • 4
    • 72749083602 scopus 로고    scopus 로고
    • D. F. Kastanya, Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator, Ph. D. Disseration, North Carolina State University, Department of Nuclear Engineering (2002).
    • D. F. Kastanya, "Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator," Ph. D. Disseration, North Carolina State University, Department of Nuclear Engineering (2002).
  • 5
    • 0003697267 scopus 로고    scopus 로고
    • Higher Order Generalized Perturbation Theory for BWR In-Core Nuclear Fuel Management Optimization,
    • PhD thesis, North Carolina State University, Department of Nuclear Engineering, Raleigh, NC
    • B. R. Moore, "Higher Order Generalized Perturbation Theory for BWR In-Core Nuclear Fuel Management Optimization," PhD thesis, North Carolina State University, Department of Nuclear Engineering, Raleigh, NC, 1996.
    • (1996)
    • Moore, B.R.1
  • 6
    • 72749089355 scopus 로고    scopus 로고
    • B. Collins-Sussman, B. W. Fitzpatrick, C. M. Pilato, Version Control with Subversion, ISBN 10: 0-596-00448-6 | ISBN 13: 9780596004484, O'Reilly Media, Inc. June 2004.
    • B. Collins-Sussman, B. W. Fitzpatrick, C. M. Pilato, "Version Control with Subversion," ISBN 10: 0-596-00448-6 | ISBN 13: 9780596004484, O'Reilly Media, Inc. June 2004.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.