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1
Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation
Published 2021-07-01Subjects: Get full text
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2
Simulation of Small-Break Loss-of-Coolant Accident Using the RELAP5 Code with an Improved Wall Drag Partition Model for Bubbly Flow
Published 2024-11-01Subjects: Get full text
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3
Analysis of natural circulation characteristics for pool-type fast reactor system
Published 2025-03-01Subjects: “…RELAP5 code…”
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