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Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
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Thông tin tài liệu:
The main purpose of this work is to use the MTR_PC package to evaluate the effect of the partially insertion of the control rod on the neutronic parameters at the operating core of the Tehran Research Reactor. The simulation results show that by increasing the insertion of control rods (bank) in the core, the absolute values of power peaking factor, reactivity coefficients and effective delayed neutron fraction increased and only prompt neutron life time decreased.
Nội dung trích xuất từ tài liệu:
Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
Nội dung trích xuất từ tài liệu:
Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
Tìm kiếm theo từ khóa liên quan:
Nuclear engineering and technology Neutronic analysis of control rod effect on safety parameters Tehran Research Reactor The control shim safety rods Power peaking factor Moderator temperature coefficientTài liệu liên quan:
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