McCARD for Neutronics Design and Analysis of Research Reactor Cores
1 Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 151-744, Korea
2 Korea Atomic Energy Research Institute, 989-111 Daedeok-Daero, Yuseong-gu, Daejeon 305-353, Korea
* Corresponding Author, E-mail: firstname.lastname@example.org
McCARD is a Monte Carlo (MC) neutron-photon transport simulation code developed exclusively for the neutronics design and analysis of nuclear reactor cores. McCARD is equipped with the hierarchical modeling and scripting functions, the CAD-based geometry processing module, the adjoint-weighted kinetics parameter and source multiplication factor estimation modules as well as the burnup analysis capability for the neutronics design and analysis of both research and power reactor cores. This paper highlights applicability of McCARD for the research reactor core neutronics analysis, as demonstrated for Kyoto University Critical Assembly, HANARO, and YALINA.
Key words: McCARD / Research Reactor / Python script / CAD-based Geometry Processing / Kinetics Parameter
© Owned by the authors, published by EDP Sciences, 2014