원문정보
초록
영어
The Cable-In-Conduit-Conductor (CICC) for the ITER tokamak Central Solenoid (CS) has undergone design change since the first prototype conductor sample was tested in 2010. After tests showed that the performance of initial conductor samples degraded rapidly without stabilization, an alternate design with shorter sub-cable twist pitches was tested and discovered to satisfy performance requirements, namely that the minimum current sharing temperature (Tcs) remained above a given limit under DC bias. With consistent successful performance of ITER CS conductor CICC samples using the alternate design, an attempt is made here to revisit the internal electromagnetic properties of the CICC cable design to identify any correlation with conductor performance. Results of this study suggest that there may be a simple link between the Nb3Sn CICC internal self-field and its Tcs performance. The study also suggests that an optimization process should exist that can further improve the performance of Nb3Sn based CICC.
목차
1. BACKGROUND
2. INTRODUCTION TO ITER CS CONDUCTOR DESIGN AND PERFORMANCE
3. SIMPLE MODEL OF CICC CABLE AND ITSMAGNETOSTATIC FIELD
3.1. Basic Principles and First Stage Sub-cable Model
3.2. Second and Subsequent Stage Sub-cable
3.3. Longitudinal Current in Final Cable
3.4. Resulting Internal Self-field of Cable
3.5. Discussion on Validity of the Model
4. COMMENTS ON THE CALCULATIONS ON CICC CABLE LAYOUTS
4.1. Comparisons between ITER CS CICC Cable Designs
4.2. Calculations for ITER TF Type Conductor Cable
4.3. Calculations on Square and Rectangular CICC Cable
5. DISCUSSION OF THE RESULTS
5.1. Trends and Correlation with Tcs Performance
5.2. Possible Link with Strand Strain Relaxation
5.3. Absence of a Definitive Explanation on Tcs Behavior
6. OTHER IDENTIFIED FACTORS IN CICC PERFORMANCE
7. CONCLUSION
ACKNOWLEDGMENT
REFERENCES