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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：59.16(Nuclear Science & Technology)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：78.82(Nuclear Science & Technology)Cristescu, I. R.*; Travis, J.*; Iwai, Yasunori; Kobayashi, Kazuhiro; Murdoch, D.*
Fusion Science and Technology, 48(1), p.464 - 467, 2005/07
Times Cited Count：3 Percentile：24.22(Nuclear Science & Technology)A model to simulate tritium behaviour after a release into a confined ventilated volume has been developed. The model assumes that for the investigated cases, tritium behaviour can be characterized by solving the dynamic equations of motion (the compressible Navier-Stokes equations) coupled with the classical k-
turbulence model to simulate the ventilation in the room and mass diffusion for tritium spreading. The GASFLOW-II fluid dynamics field code, developed through a Los Alamos National Laboratory (LANL) - Forschungszentrum Karlsruhe co-operation, was used as the computational tool to solve the equations that describe the processes. The numerical results have been validated with experimental data collected on the experimental facility (Caisson) at the Tritium Process Laboratory (TPL) Japan. Additionally an investigation of the influence of the obstacles to the tritium distribution inside the Caisson is presented.
Yoshida, Hiroshi; Glugla, M.*; Hayashi, Takumi; L
sser, R.*; Murdoch, D.*; Nishi, Masataka; Haange, R.*
Fusion Engineering and Design, 61-62, p.513 - 523, 2002/11
Times Cited Count：28 Percentile：84.16(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 
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.
