کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1728522 1521134 2014 10 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Design of a passive residual heat removal system for the FUJI-233Um molten salt reactor system
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Design of a passive residual heat removal system for the FUJI-233Um molten salt reactor system
چکیده انگلیسی


• A passive decay heat removal system for a small molten salt reactor is analyzed.
• The system uses water as a coolant and an air cooler as final heat sink.
• If the diameter of the coolant pipes is chosen correctly, problems of thermal shock can be avoided.
• Safe cooling for a period of at least 10 days can be achieved.
• The possibility of draining the primary system is an important safety feature of molten salt reactors.

This paper discusses the design and analysis of a passive decay heat removal system for a Molten Salt Reactor (MSR) of 450 MWth. Following the disaster at the Fukushima-1 nuclear power station, it is clear that the public will demand improved safety performance if nuclear power is to be accepted as a sustainable source of CO2-free energy. In this scope, thorium-based MSRs have very promising properties in the area of passive safety, resource availability and proliferation resistance. Molten Salt Reactor (MSR) systems can be equipped with an emergency salt drain tank. Under any severe accident, all the fuel salt can be drained by gravity into the drain tank, thus, the primary system can be safely emptied of fissile materials and fission products. The ultimate safety can be assured by the integrity of the fuel salt in the drain tank or in other words, the capability of residual heat removal from the fuel salt in the drain tank. From this point of view, we investigated the feasibility of a passive residual heat removal system for the drain tank of an MSR (FUJI-233Um of 450 MWth). We concluded that a system comprising a large drain tank and 60, large-diameter coolant tubes can withstand the thermal shock due to the hot fuel salt, and therefore we conclude that system is feasible.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 64, February 2014, Pages 398–407
نویسندگان
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