Similar Items: Japanese contribution of iter PF systems design during CDA.
- CDA Publication
- Assessment of TRAC-PF1/MOD1 and TRAC-PF1/MOD2 codes for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with an inclined radial power distribution.
- Physics design of an ICRF [Ion Cyclotron Range of Frequencies] system for ITER.
- Conceptual design of iter shielding blanket.
- Assesment of TRAC-PF1/MOD1 code for core thermal hydraulic behavior during reflood with CCTF and SCTF data.
- Test program development for iter blanket design.