Thermal-fluid assessment of the design options for reactor vessel cooling in a prismatic core VHTR |
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Authors: | Min-Hwan Kim Nam-il TakHong-Sik Lim |
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Affiliation: | Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yoseong, Daejeon 304-353, Republic of Korea |
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Abstract: | The design of the reactor pressure vessel is an important issue in the VHTR design due to its high operating temperature. The extensive experience base in Light Water Reactor makes SA508/533 steel emerge as a strong candidate for the VHTR reactor vessel but requires maintaining the vessel temperature below the ASME code limit. To meet the temperature requirement, three types of vessel cooling options for a prismatic core VHTR are considered: an internal vessel cooling, an external vessel cooling, and an internal insulation. The performances of the vessel cooling options are evaluated by using a system thermo-fluid analysis code and a commercial computational fluid dynamics code during normal operation and accidents. The results suggested that the internal vessel cooling with the modified inlet flow path will be a promising option. The external cooling option does not ensure an effective cooling of the RPV. The insulation option provides an effective reduction of the RPV temperature in the normal and accident conditions but reduces the fuel safety margin during the accidents, requiring careful consideration before the implementation. |
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Keywords: | Reactor vessel cooling Prismatic core VHTR Internal cooling External cooling Insulation |
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