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- [41] Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER [J]. PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 6, 2011, : 553 - 557
- [43] Neutronics features of a dual coolant lithium lead test blanket module for ITER [J]. 21ST IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING - SOFE 05, 2006, : 275 - 278
- [50] Preliminary Thermo-Hydraulic Analysis of the Breeder Zone for the EU Helium Cooled Pebble Bed Test Blanket Module for ITER [J]. 2009 23RD IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, 2009, : 380 - 383