In-vessel design of ITER diagnostic neutron activation system

Area of Science:

• Nuclear Engineering
• Plasma Physics
• Fusion Energy

Background:

• ITER requires accurate measurement of total fusion power.
• Existing methods may face challenges with ITER's asymmetric, elongated plasma.
• Neutron activation analysis is a key diagnostic technique.

Purpose of the Study:

• To implement a neutron activation system for evaluating ITER's total fusion power.
• To optimize measurement accuracy for complex plasma geometries.
• To determine optimal positions for irradiation ends.

Main Methods:

• Utilizing an encapsulated metal sample technique for neutron activation.
• Investigating physical and technical aspects of seven irradiation end locations per poloidal section.
• Performing Monte Carlo neutronic calculations for design optimization.

Main Results:

• Defined optimal positions for seven irradiation ends per poloidal section.
• Assessed physical characteristics and optimized irradiation end designs.
• Minimized measurement uncertainty for asymmetric, elongated plasma.

Conclusions:

• The proposed neutron activation system is suitable for evaluating ITER fusion power.
• Optimized irradiation end placement enhances measurement accuracy.
• Monte Carlo simulations are crucial for system design and validation.