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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2012.1
- 수록면
- 161 - 176 (16page)
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McCARD is a Monte Carlo (MC) neutron-photon transport simulation code. It has been developed exclusively for the neutronics design of nuclear reactors and fuel systems. It is capable of performing the whole-core neutronics calculations, the reactor fuel burnup analysis, the few group diffusion theory constant generation, sensitivity and uncertainty (S/U) analysis, and uncertainty propagation analysis. It has some special features such as the anterior convergence diagnostics, real variance estimation, neutronics analysis with temperature feedback, B1 theory-augmented few group constants generation, kinetics parameter generation and MC S/U analysis based on the use of adjoint flux. This paper describes the theoretical basis of these features and validation calculations for both neutronics benchmark problems and commercial PWR reactors in operation.
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참고문헌 (26)
참고문헌 신청
A. G. Croff / 1980 / A User's Manual for ORIGEN2 Computer Code
Chang Hyo Kim / 2005 / Neutronics Design and Performance Analysis of Korean ITER TBM by Monte Carlo Method
D. H. Hahn / 2007 / KALIMER-600 Conceptual Design Report
E. M. Gelbard / 1990 / Computation of Standard Deviations in Eigenvalue Calculations / Prog. Nucl. Energy 24 : 237 ~
H. J. Park / 2009 / Monte Carlo Depletion and Uncertainty Analyses for a TRU Fuel Assembly Using JENDL 3.3 Covariance Data / M&C 2009-International Conference on Mathematics,
Chang Hyo Kim / 2005 / Neutronics Design and Performance Analysis of Korean ITER TBM by Monte Carlo Method
D. H. Hahn / 2007 / KALIMER-600 Conceptual Design Report
E. M. Gelbard / 1990 / Computation of Standard Deviations in Eigenvalue Calculations / Prog. Nucl. Energy 24 : 237 ~
H. J. Park / 2009 / Monte Carlo Depletion and Uncertainty Analyses for a TRU Fuel Assembly Using JENDL 3.3 Covariance Data / M&C 2009-International Conference on Mathematics,
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