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Volumn , Issue , 2004, Pages 69-78

Coupled calculations using the numerical nuclear reactor for integrated simulation of neutronic and thermal-hydraulic phenomena

Author keywords

CFD; Computational fluid dynamics; Core analysis; Coupled codes; High performance computing; Integral transport theory; Neutronics; Numerical reactor; Parallel computers; Reactor physics; Thermal hydraulics

Indexed keywords

COUPLED CODES; HIGH PERFORMANCE COMPUTING; INTEGRAL TRANSPORT THEORY; NEUTRONICS; NUMERICAL REACTOR; PARALLEL COMPUTERS; REACTOR PHYSICS; THERMAL-HYDRAULICS;

EID: 22344455738     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (15)

References (10)
  • 3
    • 22344439465 scopus 로고    scopus 로고
    • Methodology for coupling computational fluid dynamics and integral transport neutronics
    • (Purdue University), (ANL), Chicago, IL, April 25-29
    • J. W. Thomas, Z. Zhong, T. J. Downar (Purdue University), T. Sofu (ANL), Methodology for Coupling Computational Fluid Dynamics and Integral Transport Neutronics, PHYSOR 2004, Chicago, IL, April 25-29, 2004.
    • (2004) PHYSOR 2004
    • Thomas, J.W.1    Zhong, Z.2    Downar, T.J.3    Sofu, T.4
  • 4
    • 22344445279 scopus 로고    scopus 로고
    • The coupling of the star-Cd software to a whole-core neutron transport code decart for PWR applications
    • Purdue University, Argonne National Laboratory, Korean Atomic Energy Research Institute, SNA'03, Paris, France, September 22-24
    • J. W. Thomas, H.C. Lee, T. J. Downar, Purdue University, T. Sofu, D. P. Weber, Argonne National Laboratory, H. G. Joo, J. Y. Cho, Korean Atomic Energy Research Institute, The Coupling Of The Star-Cd Software To A Whole-Core Neutron Transport Code Decart For PWR Applications," Proc. of Intl. Conf. on Supercomputing in Nuclear Applications, SNA'03, Paris, France, September 22-24, 2003.
    • (2003) Proc. of Intl. Conf. on Supercomputing in Nuclear Applications
    • Thomas, J.W.1    Lee, H.C.2    Downar, T.J.3    Sofu, T.4    Weber, D.P.5    Joo, H.G.6    Cho, J.Y.7
  • 5
    • 0346565434 scopus 로고    scopus 로고
    • CD-Adapco Group, Melville, NY
    • STAR-CD, Version 3.150A, CD-Adapco Group, Melville, NY.
    • STAR-CD, Version 3.150A
  • 6
    • 22344437710 scopus 로고    scopus 로고
    • CFD.-ACE, CFD Research Corporation, Huntsville, Alabama
    • CFD.-ACE, CFD Research Corporation, Huntsville, Alabama.
  • 7
    • 0030190007 scopus 로고    scopus 로고
    • Doppler reactivity calculation for thermal reactor cells by space-dependent multiband method
    • T. Takeda, K. Ohya, E. Saji, Doppler Reactivity Calculation for Thermal Reactor Cells by Space-Dependent Multiband Method, J. Nucl. Sci. Technol, Vol. 33, 604, 1996.
    • (1996) J. Nucl. Sci. Technol , vol.33 , pp. 604
    • Takeda, T.1    Ohya, K.2    Saji, E.3
  • 8
    • 76149108933 scopus 로고    scopus 로고
    • High-fidelity thermal-hydraulic analysis using CFD and massively parallel computers
    • SNA-2000, Tokyo, Japan, September
    • D. P. Weber, et al., High-Fidelity Thermal-Hydraulic Analysis Using CFD and Massively Parallel Computers, 4th Intl. Conf. on Supercomputing in Nuclear Applications, SNA-2000, Tokyo, Japan, September 2000.
    • (2000) 4th Intl. Conf. on Supercomputing in Nuclear Applications
    • Weber, D.P.1
  • 9
    • 22344445402 scopus 로고
    • Mathematical modeling
    • EPRI-NP-2511-CCM, Electric Power Research Institute, Palo Alto, California, Prepared by Battelle, Pacific Northwest Laboratories, Richland, Washington, November
    • EPRI-NP-2511-CCM, Mathematical Modeling, Vol. 1: VIPRE-01, A Thermal-Hydraulic Analysis Code for Reactor Cores, Electric Power Research Institute, Palo Alto, California, Prepared by Battelle, Pacific Northwest Laboratories, Richland, Washington, November 1983.
    • (1983) VIPRE-01, A Thermal-Hydraulic Analysis Code for Reactor Cores , vol.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.