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Deuterium retention in tungsten-coated reduced activation ferritic/martensitic steel
| Content Provider | Semantic Scholar |
|---|---|
| Author | Armando, Marco |
| Copyright Year | 2014 |
| Abstract | Tungsten (W) is considered to be a good candidate as plasma-facing material of blanket in fusion reactor because of its good thermal properties and high atomic number. Despite those advantages, tungsten is a very heavy material. In order to solve this problem, tungsten coating on plasma-facing components (PFCs) is being developed. However, the performance of the W coating should be evaluated. Ferritic steel has better compatibility with both liquid metal or solid breeder, and all candidate coolants of fusion reactors, compared to austenitic steel. It also has low thermal expansion coefficient and high thermal conductivity. Moreover, the reduced activation ferritic-martensitic steel F82H (Fe-8Cr-2W) has been developed as candidate structure material for ITER blanket because of its advantages. Hydrogen isotope retention in PFCs affects surface properties, plasma fuelling, and wall conditioning of a fusion reactor and greatly depends on the material. Therefore there is a need to evaluate the deuterium retention/desorption behaviour of the tungsten coating, especially on F82H. |
| File Format | PDF HTM / HTML |
| Alternate Webpage(s) | http://www.eng.hokudai.ac.jp/e3/alumni/files/abstract/m311.pdf |
| Language | English |
| Access Restriction | Open |
| Content Type | Text |
| Resource Type | Article |
