کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
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1741479 | 1017393 | 2010 | 11 صفحه PDF | دانلود رایگان |
A conceptual sodium-cooled fast reactor (KALIMER-600) has been developed at KAERI. In this work, the simplified performance analysis code for the KALIMER-600 was developed and the power maneuvering characteristics without control rod movement was evaluated. We developed the analysis code by modifying a commercial Modular Modeling System (MMS) code. We attached the library for the properties of sodium as an additional user library and modified some component modules such as the fuel and pipehx with specific features of KALIMER-600.Then, the power maneuvering capability without control rod movement was evaluated when the BOP (balance of plant) power was changed. We called the power maneuvering capability with inherent reactivity feedback mechanism without control rod movement as self-control. We, in turn, evaluated the self-control capability under varied and/or fixed the flow rate of the coolant systems of the plant. We concluded the KALIMER-600 had a good self-control capability and some data obtained from this study would be used in developing control rod programming and flow rate programming of plant during power maneuvering.
Journal: Progress in Nuclear Energy - Volume 52, Issue 7, September 2010, Pages 655–665