Speaker
XINGHUA WU
(CHINA)
Description
Currently there are a lot of code and standards for nuclear facilities and pressure vessels, i.e. ASME BPVC III, ASME BPVC VIII, RCC-MR/MRx, EN 13445, GB/T 150, etc. The design rules are not quite consistent, especially for definition of allowable stresses, hydrostatic pressure, welding joint coefficient, elastic analysis criteria. In this presentation, the rules from different standards are compared, and current application of RCC-MRx on design and fabrication of CN ITER HCCB TBM-set is introduced also.
| Technical Categories Addressed | Tritium breeder blankets (ex. molten salts, liquid metals) |
|---|---|
| Speaker's title | Mr |
| Speaker's email address | wuxh@swip.ac.cn |
| Country/Int. organization | China |
| Affiliation/Organization | 核工业西南物理研究院 |
Author
XINGHUA WU
(CHINA)
