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1
Coupled heat and mass transfer simulation of CRUD migration and deposition in PWR systems
Published 2025-02-01Subjects: Get full text
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2
Critical evaluation of accident tolerant fuel selection criteria for APR-1400 nuclear reactors
Published 2025-12-01Subjects: “…PWR…”
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3
Leak-Before-Break methodology applied to different piping materials: a performance evaluation
Published 2019-08-01Subjects: Get full text
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4
Leak-Before-Break methodology applied to different piping materials: a performance evaluation
Published 2019-10-01Subjects: Get full text
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Assemblies design and modeling analysis of a new fine mesh neutronics/thermal-hydraulics coupling benchmark for plate-type PWR core
Published 2025-02-01Subjects: “…Plate-type PWR with high parameters…”
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