Modified blanket cooling manifold system for ITER

Dust Removal Experiments for ITER Blanket Remote Handling System

To reduce maintenance workers’ dose rate caused by activated dust adhering to the ITER blanket remote handling system (BRHS), dust must be removed from BRHS surfaces. Dust that adheres to the top surface of the BRHS rail from cyclic loading of the vehicle manipulator is considered to be the most difficult dust to remove. Dust removal experiments were conducted to simulate the materials, conditi...

Tritium Modeling for Iter Test Blanket Module

HCPB (Helium Cooled Pebbles Bed) Test Blanket Model (TBM) is based on solid breeder. Tritium has to be extracted using Helium purge gas flowing through breeder pebbles bed. He-stream must be cooled down and processed and all these steps are carried out in TES (Tritium Extraction System). A modeling work has been performed to study the behavior of the TES of the HCPB TBM and for Molecular Sieve ...

US Plans and Strategy for ITER Blanket Testing

Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) ...

An Assessment of the Base Blanket for Iter

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in the CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has man...

UWFDM-1257 US Plans and Strategy for ITER Blanket Testing