메뉴 건너뛰기




Volumn 2, Issue , 2008, Pages 901-907

An optimized ultra-fine energy group structure for neutron transport calculations

Author keywords

[No Author keywords available]

Indexed keywords

EIGENVALUES AND EIGENFUNCTIONS; MONTE CARLO METHODS; NEUTRON FLUX; REACTION RATES; RESONANCE; SHIELDING; TRANSPORT PROPERTIES;

EID: 79953867943     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (10)

References (11)
  • 5
    • 0005334182 scopus 로고
    • Processing and Application of ENDF/B-VI in LWRs
    • Fredin B., et al., Processing and Application of ENDF/B-VI in LWRs, Trans. Am. Nucl. Soc., 73, 419(1995)
    • (1995) Trans. Am. Nucl. Soc. , vol.73 , pp. 419
    • Fredin, B.1
  • 6
    • 79953892529 scopus 로고    scopus 로고
    • Determination of the Optimized SHEM Mesh for Neutron Transport Calculations
    • Hfaiedh N. and Santamarina A., Determination of the Optimized SHEM Mesh for Neutron Transport Calculations, Trans. Am. Nucl. Soc.,(2005)
    • (2005) Trans. Am. Nucl. Soc.
    • Hfaiedh, N.1    Santamarina, A.2
  • 8
    • 24944486847 scopus 로고    scopus 로고
    • Development of Spatially Dependent Resonance Shielding Method
    • Matsumoto H., et al., Development of Spatially Dependent Resonance Shielding Method, J. of Nucl. Sc. And Tech., 42, 8, 688(2005)
    • (2005) J. of Nucl. Sc. And Tech. , vol.42 , Issue.8 , pp. 688
    • Matsumoto, H.1
  • 11
    • 79953860611 scopus 로고    scopus 로고
    • Overview and Theory
    • X-5 Monte Carlo Team, Version 5 LA-UR-03-1987
    • X-5 Monte Carlo Team, "MCNP" - A general Monte Carlo N-Particle Transport Code, Version 5, Volume I: Overview and Theory, LA-UR-03-1987 (2003)
    • (2003) "MCNP" - A General Monte Carlo N-Particle Transport Code , vol.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.