10 ITER agreement tasks have
been undertaken at SWIP, five of them have achieved their goals. The R&D
of four ITER tasks (first wall and shielding blanket, magnet gravity
support, gas injection and glow discharge cleaning system, neutron flux
measurement) has been carried out. For example the technology for
manufacturing high purity (>99%) ITER specified Be plate and CuCrZr
alloy is obtained, their major mechanical and physical properties were
measured. Besides, the static stress of the gravity support system for
ITER was simulated by the finite element method（FEM）.
A neutron generator for the calibration of the neutron flux monitoring
was designed in detail.
has planned to develop own ITER TBM （test
modules for testing during ITER operation period, the design of ITER TBM
is also in progressing, helium-cooled/solid tritium breeder (HCSB) with
the pebble bed concept has been adopted in Chinese TBM module design. 3
dimensional structure models of HCSB TBM have been designed. A
structural material named as CLF-1, a type of reduced activation
ferritic/martenstic steel, was developed. Besides, some progress in
fusion reactor design and related technology was achieved. It is
includes study of high Z plasma facing materials such as W＋Si
coating, experimental investigation of liquid metal blanket
such as flow channel insert to reduce MHD effects and so on. The
conceptual design for the ceramic breeder DEMO power plant（HCSB-DEMO）has
been carried out.