1. Single-side conduction modeling for high heat flux coolant channels;Boyd;Fusion Technol.,1999
2. Modeling the Nukiyama curve for water-cooled fusion divertor channels;Marshall;Fusion Technol.,2001
3. A new facility for measurements of three-dimensional, local subcooled flow boiling heat flux and related critical heat flux;Boyd,2000
4. Round robin CHF testing of an ITER vertical target swirl tube;Youchison,1999
5. Development of high heat flux components in JAERI;Akiba,1999