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Development and validation of an advanced thermal-hydraulic analysis program for helical coil once-through steam generator in lead-based cooled fast reactor
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DOI：10.1016/j.pnucene.2026.106499.png)
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Abstract
En 中文
• An advanced transient analysis code is developed for HCOTSG based on two-fluid model. • The validation of primary side of HCOTSG is done to verify the program. • The steady-state and transient verifications are finished to verify the models. • The program may be useful for the design and safety analysis of HCOTSG.
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