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Journal Articles

Fuel cycle design for ITER and its extrapolation to DEMO

Konishi, Satoshi*; Glugla, M.*; Hayashi, Takumi

Fusion Engineering and Design, 83(7-9), p.954 - 958, 2008/12

 Times Cited Count:16 Percentile:70.89(Nuclear Science & Technology)

Journal Articles

Evolution of ITER tritium confinement strategy and adaptation to Cadarache site conditions and French regulatory requirements

Murdoch, D.*; Glugla, M.*; Hayashi, Takumi; Perevesentsev, A.*; Stephan, Y.*; Taylor, C.*

Fusion Engineering and Design, 83(10-12), p.1355 - 1358, 2008/12

 Times Cited Count:11 Percentile:59.25(Nuclear Science & Technology)

Journal Articles

ITER design review; Tritium issues

Murdoch, D.*; Beloglazov, S.*; Boucquey, P.*; Chung, H.*; Glugla, M.*; Hayashi, Takumi; Perevezentsev, A.*; Sessions, K.*; Taylor, C.*

Fusion Science and Technology, 54(1), p.3 - 8, 2008/07

 Times Cited Count:21 Percentile:78.91(Nuclear Science & Technology)

Journal Articles

Comparison of tritium retention and carbon deposition in JET and JT-60U

Tanabe, Tetsuo*; Sugiyama, Kazuyoshi*; Coad, P.*; Bekris, N.*; Glugla, M.*; Miya, Naoyuki

Journal of Nuclear Materials, 345(2-3), p.89 - 95, 2005/10

 Times Cited Count:17 Percentile:73.56(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Tritium retention of plasma facing components in tokamaks

Tanabe, Tetsuo*; Bekris, N.*; Coad, P.*; Skinner, C. H.*; Glugla, M.*; Miya, Naoyuki

Journal of Nuclear Materials, 313-316, p.478 - 490, 2003/03

 Times Cited Count:67 Percentile:96.51(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Design of the ITER tritium plant, confinement and detritiation facilities

Yoshida, Hiroshi; Glugla, M.*; Hayashi, Takumi; L$"a$sser, R.*; Murdoch, D.*; Nishi, Masataka; Haange, R.*

Fusion Engineering and Design, 61-62, p.513 - 523, 2002/11

 Times Cited Count:26 Percentile:84.19(Nuclear Science & Technology)

ITER tritium plant is composed of tokamak fuel cycle systems, tritium confinement and detritation systems. The tokamak fuel cycle systems, composed of various tritium sumsystems such as vacuum vessel cleaning gas processing, tokamak exhaust processing, hydrogen isotope separation, fuel storage, mixing and delivery, and external tritium receiving and long-term storage, has been designed to meet not only ITER operation scenarios but safety requirements (minimization of equipment tritium inventory and reduction of environmental tritium release at different off-normal events and accident scenarios). Multiple confinement design was employed because tritium easily permeates through metals (at $$>$$ 150 $$^{circ}$$C) and plastics (at ambient temperature) and mixed with moisture in room air. That is, tritium process equipment and piping are designed to be the primary confinement barrier, and the process equipments (tritium inventory $$>$$ 1 g) are surrounded by the secondary confinement barrier such as a glovebox. Tritium process rooms, which contains these facilities, form the tertiary confinement barrier, and equipped with emergency isolation valves in the heating ventillation and air conditioning ducts as well as atmosphere detritiation systems. This confinement approach has been applied to tokamak building, tritium building, and hotcell and radwaste building.

Oral presentation

Design of LPCE column for performance tests on tritium separation with TLK facility

Sugiyama, Takahiko*; Yamanishi, Toshihiko; Munakata, Kenzo*; Asakura, Yamato*; Yamamoto, Ichiro*; Glugla, M.*

no journal, , 

We report a design of the column interior which was designed to fit into the existing facility dedicated for LPCE process characterization (under the limitation of the TLK facility). The experimental conditions such as liquid and gas flow-rates, temperature have been established during preliminary investigations carried out at Nagoya University. The column to be used in the TLK facility is stainless steel tube with 55 mm internal diameter and 2 m length. The tritium separation experiments are performed at 120 kPa, 343 K. A stage-wise model was also developed to predict separative performance of the column. This model requires the channeling coefficients. The channeling coefficient which represents axial dispersion of the packed bed is evaluated against flow rates of water by impulse response. Analytical results with the present model present effects of the catalysis quantity and the gas-liquid ratio on separative performances of the column.

Oral presentation

Recent progress in ITER tritium plant systems design and layout

Glugla, M.*; Beloglazov, S.*; Carlson, B.*; Cho, S.*; Cristescu, I.*; Cristecu, I.*; Chung, H.*; Girard, J.-P.*; Hayashi, Takumi; Mardoch, D.*; et al.

no journal, , 

Oral presentation

Tritium retention buildup towards pulses in ITER PFCs and dust

Shu, Wataru; Ciattaglia, S.*; Glugla, M.*

no journal, , 

no abstracts in English

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