EXTENDING CTF MODELING CAPABILITIES TO SFRs AND VALIDATION AGAINST SHRT TESTS
نویسندگان
چکیده
The utilization of liquid metals as coolants for fast reactors brings several economical and practical advantages that lead to a sustainable future nuclear energy. Molten sodium is used coolant in Sodium Fast Reactors (SFRs). relatively cheaper than other metal coolants. It requires lower pumping power, causes less neutron moderation it non-corrosive the fuel cladding. SFR hexagonal subassemblies are smaller Light Water (LWRs) subassemblies. differences geometrical design SFRs compared LWRs different physical behavior coolant. Several models correlations particular were implemented thermal-hydraulics (TH) computer codes order model accurately. CTF subchannel TH code was designed validated LWRs. In this work, capabilities extended by incorporating properties friction factor, flow mixing coefficient conduction heat transfer. then against selected steady state data from Experimental Breeder Reactor II Shutdown Heat Removal Tests SHRT-17 SHRT-45R. simulate instrumented XX09 XX10. results demonstrate capability SFRs. Code validation currently being transient phases SHRT experiments.
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ژورنال
عنوان ژورنال: Epj Web of Conferences
سال: 2021
ISSN: ['2101-6275', '2100-014X']
DOI: https://doi.org/10.1051/epjconf/202124710034