SF/sub 6/ and water cold trap for TFTR deuterium-tritium operations

M. Viola, L. Dudek, V. Garzotto, J. Kamperschroer, G. Martin, R. Rossmassler, R. Sissingh
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引用次数: 1

Abstract

The Tokamak Fusion Test Reactor (TFTR) vacuum system is being upgraded to trap SF/sub 6/ gas which may leak from the neutral beam injectors during the planned deuterium-tritium experiments. This is necessary since SF/sub 6/ can, in 25% of a gram-mole, completely inactivate the platinum catalyst in the tritium cleanup system (TCS). Any SF/sub 6/ leaking into the injectors will initially be held on the liquid helium or liquid nitrogen cryopanels. During regens of the liquid helium panel, the deuterium and tritium will pass to the TCS, with the SF/sub 6/ being retained on the cryopanels. In the final phase of the accident recovery scenario, the cryopanels will be warmed to room temperature and the SF/sub 6/ collected by a liquid-nitrogen cooled cold trap. Design of the cold trap and measurements of the vapor pressure of SF/sub 6/ at 77 K as a function of surface coverage are presented. The SF/sub 6/ vapor pressure at 77 K, with only a few monolayers absorbed, was found to be <10/sup -7/ torr. Modest pressures of approximately 10/sup -5/ torr were measured after nearly 3*10/sup 5/ torr-1 were deposited on a cold trap with an area of 0.1 m/sup 2/. In the final configuration, the cold trap will also be used to collect water which may have accidentally leaked into the vacuum system.<>
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SF/ sub6 /和水冷阱用于TFTR氘-氚操作
托卡马克聚变试验反应堆(TFTR)真空系统正在升级,以捕获在计划中的氘-氚实验中可能从中性束注入器泄漏的SF/sub - 6/气体。这是必要的,因为SF/sub 6/在25%克摩尔的情况下,可以完全使氚净化系统(TCS)中的铂催化剂失活。任何泄漏到喷射器中的SF/sub / 6将首先被保存在液氦或液氮低温板上。在液氦板的再生过程中,氘和氚将传递到TCS,而SF/sub / 6将保留在低温板上。在事故恢复方案的最后阶段,低温面板将被加热到室温,SF/sub 6/将由液氮冷却冷阱收集。介绍了冷阱的设计和77 K时SF/sub 6/的蒸汽压随表面覆盖的函数的测量结果。77 K时的SF/sub 6/蒸气压为>,仅吸收了少量单层膜
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Design of a coil to correct magnetic field errors on the DIII-D tokamak The charge exchange recombination diagnostic system on the DIII-D tokamak Software upgrade for the DIII-D neutral beam control systems Timing system for neutral beam injection on the DIII-D tokamak DIII-D radiation shielding procedures and experiences
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