| Budget Amount *help |
¥13,000,000 (Direct Cost: ¥10,000,000、Indirect Cost: ¥3,000,000)
Fiscal Year 2017: ¥1,820,000 (Direct Cost: ¥1,400,000、Indirect Cost: ¥420,000)
Fiscal Year 2016: ¥2,080,000 (Direct Cost: ¥1,600,000、Indirect Cost: ¥480,000)
Fiscal Year 2015: ¥1,690,000 (Direct Cost: ¥1,300,000、Indirect Cost: ¥390,000)
Fiscal Year 2014: ¥7,410,000 (Direct Cost: ¥5,700,000、Indirect Cost: ¥1,710,000)
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| Outline of Final Research Achievements |
ITER will use Be as a main chamber wall material and W as a divertor material. To examine the performances of these materials in tokamak environment, JET in EU has performed ITER-Like Wall (ILW) experimental campaigns with Be main chamber tiles and W-coated CFC divertor tiles. In this study, tritium (T) distributions on these tiles were examined using imaging plate (IP) technique and beta-ray induced X-ray spectrometry. Two retention mechanisms were found: (1) co-deposition with Be and other impurities, and (2) implantation into material bulk. T concentrations in Be deposition layers were lower than those in carbon deposition layers formed in previous campaigns with carbon tiles. Far less co-deposition of T on the sides of tiles was observed for ILW tiles compared with carbon tiles. Significantly reduced T retention was expected with Be and W walls in comparison with C walls. Technique to measure T retention in an individual dust particle using IP was also developed.
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