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A New View of Extended Capabilities of the COREP Code
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作者 M. Kromar 《Journal of Energy and Power Engineering》 2011年第2期184-188,共5页
The COREP (CORE Power) code has been developed by the Reactor Physics Department of the Jozef Stefan Institute for the nuclear design calculations of the PWR (Pressurized Water Reactor) cores. The code and applied... The COREP (CORE Power) code has been developed by the Reactor Physics Department of the Jozef Stefan Institute for the nuclear design calculations of the PWR (Pressurized Water Reactor) cores. The code and applied methods have been developed and tested only for the determination of the pin power in the reactor core. Recent development of the three dimensional visualization capabilities at the author's department enables fine mesh neutron flux and power distribution presentation in the whole reactor region. The COREP code has been supplemented with additional option to enable generation of fme mesh neutron flux data in the core and reflector domain. Accuracy of the generated fine mesh results has been determined for the 2-D IAEA and typical NPP Krsko case. 展开更多
关键词 PWR nodal diffusion solver flux distribution pin power reconstruction
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