Thermo-Structural Analysis of CLAM Steel and SS316L in the First Wall for ITER during Thermal Cycling

Abstract:

The temperature and strain distributions of the mockup composed of Be, Cu-alloy with distinct structural material (SS316L and China Low Activation martensitic steel (CLAM)) were calculated and analyzed during thermal cycling, based on a high heat flux (HHF) test recently reported with heat flux of 1.5MW/m2. The calculated temperature and strain results, in which SS316L is as the structural material, showed a good agreement with HHF test. By substituting CLAM steel for SS316L the contrast analysis indicates that the thermo-mechanical property for CLAM steel is better than that of SS316 at the same condition. Furthermore, the temperature and strain distributions of the FW were calculated under the condition of normal ITER operation: the surface heat flux is about 0.5MW/m2 and volumetric heating due to neutron radiation is on the order of 15~20 MW/m2.

• Periodical: Advanced Materials Research (Volumes 152-153)
• Pages: 1716-1720
• DOI: https://doi.org/10.4028/www.scientific.net/AMR.152-153.1716
• Online since: October 2010
• Authors: Fu Bin Liu, Man Yao, Peng Bo Zhang, Ji Jun Zhao
• Keywords: First Wall, ITER, Reduced Activation Ferritic Martensitic, Thermo-Structural Analysis

References

[1] Dong Won Lee, Young Dug Bae and Suk Kwon Kim: Fus. Eng. Des. Vol. 84(2009), pp.573-577.

[2] T. Hatanno, S. Suzuki and K. Yokoyama: Fus. Eng. Des. Vol. 39-40(1998), pp.363-370.

[3] ITER Material Properties Handbook, File code: ITER-AA02-2402.

[4] T. Hatano : Fusion Eng. Des. 39–40 (1998) 363–370.

[5] Q. Huang, C. Li and Y. Li: Journal of Nuclear Materials. Vol. 367–370 (2007), p.142–146.

[6] Jinnan Yu, Qunying Huang and Farong Wan: Journal of Nuclear Materials. Vol. 367–370 (2007), p.97–101.

[7] D. Mitin, S. Khomyakov and A. Razmerov: Fus. Eng. Des. Vol. 83(2008), pp.1188-1198.

[8] Neutron Wall Loading Distribution on the First Wall. ITER Nuclear Analysis Report. G 73 DDD 2 01-06-06 W 0. 1. (Chapter 4. 1).