메뉴 건너뛰기




Volumn 2, Issue , 2010, Pages 1483-1495

BWR modeling capability and scale/triton lattice-to-core integration of the nestle nodal simulator

Author keywords

BWR; NESTLE; Nodal core simulator; SCALE; TRITON

Indexed keywords

COMPUTER SOFTWARE; PRESSURIZED WATER REACTORS; REACTOR CORES; SIMULATORS;

EID: 79952391616     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (6)

References (15)
  • 1
    • 0003894050 scopus 로고    scopus 로고
    • ORNL/TM-2005/39, Version 5.1, November 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.
    • (2006) SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations , vol.1-3
  • 3
    • 51849100460 scopus 로고
    • 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, et al., "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
  • 8
    • 79952385543 scopus 로고    scopus 로고
    • A Powerful and Affordable Computational Infrastructure for Nuclear Engineering Education and Research, under Review
    • October
    • D. D. Dixon, J.D. Galloway, G.I. Maldonado, "A Powerful and Affordable Computational Infrastructure for Nuclear Engineering Education and Research," Under Review: ASEE Journal of Engineering Technology, October 2009.
    • (2009) ASEE Journal of Engineering Technology
    • Dixon, D.D.1    Galloway, J.D.2    Maldonado, G.I.3
  • 13
    • 48149113972 scopus 로고    scopus 로고
    • Validation of the sub-channel code F-COBRA-TF Part I. Recalculation of single-phase and two-phase pressure loss measurements
    • M. Gluck, "Validation of the sub-channel code F-COBRA-TF Part I. Recalculation of single-phase and two-phase pressure loss measurements," Nuclear Engineering and Design, 238, 2308 (2008).
    • (2008) Nuclear Engineering and Design , vol.238 , pp. 2308
    • Gluck, M.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.