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- [42] DEVELOPMENT OF THERMAL-HYDRAULIC AND SAFETY ANALYSIS CODE FOR A HEAT PIPE COOLED REACTOR PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 4, ICONE31 2024, 2024,
- [45] Thermal Hydraulics of Accelerator-Driven System Using RELAP5 Code JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2015, 1 (04):
- [48] A NEUTRONICS CONCEPT DESIGN OF LEAD-BISMUTH COOLED ACCELERATOR-DRIVEN SYSTEM FOR MINOR ACTINIDE TRANSMUTATION PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2, 2014,