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Showing results 1 to 5 of 5

1
Comparison of the structure of the plasma-facing surface and tritium accumulation in beryllium tiles from JET ILW campaigns 2011-2012 and 2013-2014

Pajuste, Elina; Jeong, C.; Kwak, Sehyun, NUCLEAR MATERIALS AND ENERGY, v.19, pp.131 - 136, 2019-05

2
Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module

Cho, Seung-Yon; Ahn, Mu-Young; Kim, Duck-Hoi; Lee, Eun-Seok; Yun, Sung-Hwan; Cho, Nam-Zin; Jung, Ki-Jung, FUSION ENGINEERING AND DESIGN, v.83, no.7-9, pp.1163 - 1168, 2008-12

3
Prediction of tritium behavior in the atmosphere and assessment of radiological impact = 삼중수소의 대기중 거동 및 그 영향에 관한 연구link

Rho, Byung-Hwan; 노병환; et al, 한국과학기술원, 1998

4
Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign

Hatano, Y; Jeong, C; Kwak, Sehyun, NUCLEAR MATERIALS AND ENERGY, v.18, pp.258 - 261, 2019-01

5
Tritium retention characteristics in dust particles in JET with ITER-like wall

Otsuka, T.; Masuzaki, S.; Ashikawa, N.; Hatano, Y.; Asakura, Y.; Suzuki, Tatsuya; Suzuki, Takumi; et al, NUCLEAR MATERIALS AND ENERGY, v.17, pp.279 - 283, 2018-12

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