메뉴 건너뛰기




Volumn 2006, Issue , 2006, Pages

Lattice physics capabilities of the SCALE code system using TRITON

Author keywords

Depletion; Lattice physics; Mixed oxide; MOX; NEWT; Validation

Indexed keywords

ASSEMBLY; COMPUTATIONAL GEOMETRY; HIGH ENERGY PHYSICS; NUCLEAR FUELS; OPTIMIZATION;

EID: 33847214931     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (14)

References (11)
  • 1
    • 33244473798 scopus 로고    scopus 로고
    • An advanced deterministic method for spent-fuel criticality safety analysis
    • Nashville, Tennessee, June 7-11, 1998. Trans. Am. Nucl. Soc
    • M. D. DeHart, "An advanced deterministic method for spent-fuel criticality safety analysis," Proc. ANS 1998 Annual Meeting and Embedded Topical Meeting, Nashville, Tennessee, June 7-11, 1998. Trans. Am. Nucl. Soc., 78, 170-172 (1998).
    • (1998) Proc. ANS 1998 Annual Meeting and Embedded Topical Meeting , vol.78 , pp. 170-172
    • DeHart, M.D.1
  • 3
    • 33847216199 scopus 로고    scopus 로고
    • Advancements in generalized-geometry discrete ordinates transport for lattice physics calculations
    • Vancouver, British Columbia, Canada, Sept. 10-14
    • M. D. DeHart, "Advancements in generalized-geometry discrete ordinates transport for lattice physics calculations," Proc. of PHYSOR-2006, Vancouver, British Columbia, Canada, Sept. 10-14, 2006.
    • (2006) Proc. of PHYSOR-2006
    • DeHart, M.D.1
  • 5
    • 33847241419 scopus 로고    scopus 로고
    • A modular code system for performing standardized computer analyses for licensing evaluation, ORNL/TM-2005/39
    • SCALE:, Version 5, Vols, April
    • SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, ORNL/TM-2005/39, Version 5, Vols. I-III, April 2005. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.
    • (2005) Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725 , vol.I-III
  • 6
    • 33847213708 scopus 로고    scopus 로고
    • O. W. Hermann and R. M. Westfall, ORIGEN-S: SCALE system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation source terms, 2, Sect. F7, of SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, ORNL/TM-2005/39, Version 5, Vols. I-III, April 2005. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.
    • O. W. Hermann and R. M. Westfall, "ORIGEN-S: SCALE system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation source terms," Vol. 2, Sect. F7, of SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, ORNL/TM-2005/39, Version 5, Vols. I-III, April 2005. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.
  • 7
    • 33847219182 scopus 로고    scopus 로고
    • Validation of SCALE/TRITON 2-D and 3-D models for LWR fuel
    • Vancouver, British Columbia, Canada, Sept. 10-14
    • S. M. Bowman and D. F. Gill, "Validation of SCALE/TRITON 2-D and 3-D models for LWR fuel," Proc. of PHYSOR-2006, Vancouver, British Columbia, Canada, Sept. 10-14, 2006.
    • (2006) Proc. of PHYSOR-2006
    • Bowman, S.M.1    Gill, D.F.2
  • 8
    • 0036699343 scopus 로고    scopus 로고
    • Benchmark problem suite for reactor physics study of LWR next generation fuels
    • A. Yamamoto et al., "Benchmark problem suite for reactor physics study of LWR next generation fuels," J. Nucl. Sci. Technol 39:8, 900-912 (2002).
    • (2002) J. Nucl. Sci. Technol , vol.39 , Issue.8 , pp. 900-912
    • Yamamoto, A.1
  • 9
    • 33344470272 scopus 로고    scopus 로고
    • Code-to-code benchmark of coolant void reactivity (CVR) in the ACR-700 reactor," 2005 ANS Winter Meeting, "Talk About Nuclear Differently: A Good Story Untold," Washington, D.C., Nov. 13-17, 2005
    • K. T. Clarno et al., "Code-to-code benchmark of coolant void reactivity (CVR) in the ACR-700 reactor," 2005 ANS Winter Meeting, "Talk About Nuclear Differently: A Good Story Untold," Washington, D.C., Nov. 13-17, 2005. Trans. Am. Nucl. Soc., 93, 977-980 (2005).
    • (2005) Trans. Am. Nucl. Soc , vol.93 , pp. 977-980
    • Clarno, K.T.1
  • 10
    • 33244484260 scopus 로고    scopus 로고
    • U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
    • F. Odar, et al., "TRACE v4.0 user's manual," U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research (2004).
    • (2004) TRACE v4.0 user's manual
    • Odar, F.1
  • 11
    • 33746220163 scopus 로고    scopus 로고
    • Analysis of decay heat measurements for BWR fuel assemblies
    • Reno, Nevada, June 4-8, 2006. Trans. Am. Nucl. Soc
    • G. Ilas and I. C. Gauld, "Analysis of decay heat measurements for BWR fuel assemblies," Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Reno, Nevada, June 4-8, 2006. Trans. Am. Nucl. Soc., 94, 385-387 (2006).
    • (2006) Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors , vol.94 , pp. 385-387
    • Ilas, G.1    Gauld, I.C.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.