'Tritium permeation' presentation slideshows

Tritium permeation - PowerPoint PPT Presentation

Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007)

Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007)

Overview of Japanese PbLi-T Research Activities and Related Topics. Takayuki Terai tera@n.t.u-tokyo.ac.jp University of Tokyo. Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007). Japanese PbLi-T Research Activities and Related Topics.

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424 views • 28 slides
Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007)

Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007)

Overview of Japanese PbLi-T Research Activities and Related Topics. Takayuki Terai tera@n.t.u-tokyo.ac.jp University of Tokyo. Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007). Japanese PbLi-T Research Activities and Related Topics.

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376 views • 28 slides
Estimation of Tritium Recovery from a Molten Salt Blanket of FFHR

Estimation of Tritium Recovery from a Molten Salt Blanket of FFHR

US/Japan Workshop on Power Plant Studies and Related Advanced Technologies with EU Participation, April 6-7, 2002 (San Diego, CA). Estimation of Tritium Recovery from a Molten Salt Blanket of FFHR. Dept. Applied Quantum Physics and Nuclear Engineering, Kyushu University Satoshi FUKADA.

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392 views • 20 slides
Tritium Control

Tritium Control

Tritium Control. A Major Issue for a Liquid Metal Blanket. Blanket modules. M LiPb. J 2. J 3. J FW. LiPb purification. h LiPb. Tritium extraction from LiPb. J 1. Pump. a Q PbLi. Q PbLi. air purification. Steam generator. J 4. J 5. h He. He purification. a Q He.

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387 views • 17 slides
Recent Progress in Helium-Cooled Ceramic Breeder (HCCB) Blanket Module R&D and Design Analysis

Recent Progress in Helium-Cooled Ceramic Breeder (HCCB) Blanket Module R&D and Design Analysis

Recent Progress in Helium-Cooled Ceramic Breeder (HCCB) Blanket Module R&D and Design Analysis. Ying, Alice With contributions from M. Narula, H. Zhang, D. Papp. FNST Meeting August 12-14, 2008 UCLA. He purge gas pipe. Be (Be 12 Ti) pebbles. Ceramic breeder pebbles.

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345 views • 16 slides
Tritium Research in TITA Information Required

Tritium Research in TITA Information Required

Tritium Research in TITA Information Required. Dai-Kai Sze, UCSD Phil Sharpe, INL Presented at the US-ITER TBM Meeting UCLA, LA, CA Feb. 14-15, 2007. Proposed Tritium Research Activities in TITAN Collaboration (formerly known as JUPITER-III).

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176 views • 16 slides
Tritium Permeation Issue, Plan and Progress

Tritium Permeation Issue, Plan and Progress

Tritium Permeation Issue, Plan and Progress. ITER. Dai-Kai Sze. University of California, San Diego Presented at the ITER TBM Project Meeting UCLA, Feb. 23-25, 2004. Statement of Problem. ITER. Fusion blankets have high tritium partial pressure.

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313 views • 9 slides

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