The operation of the TFTR tritium system

Gentile, C.; Kalish, M.; Amarescu, E.; Benson, Jerrel W.; Blanchard, W.; Bunting, C. A.; Bush, S. H.; Camp, Roderic Ai; Carpe, A.; Carnevale, R.H.; Casey, M.; Ciebiera, L.; Connell, Steve; Gibson, Marc A.; Hawryluk, R. J.; Hatcher, R.; Hawes, Rosemary; Homer, S.; Hosea, J.; Hyatt, D.; Kearns, E.; Kozub, T.; Langford, J.; Langish, S.; Marsala, R.; Montague, J.H.; Nagy, A.; Pearson, Gavin; Quigley, Michael N.; Raftopoulos, S.; Raucci, R.; Reeves, D.; Rogers, E.J.; Schobert, J.; Shaltis, D.; Sichta, P.; Such, C; Vinson, S.; Viola, M.; Halle, A. von; Walker, W.H.; Walters, T.; Williams, S.; Yager, R.

doi:10.1109/fusion.1997.687038

Cited by 3 publications

(2 citation statements)

References 2 publications

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“…During the final four years of TFTR operations, 1993 to 1997 approximately 53, 000 Ci of tritium was injected into the TFTR vacuum vessel mainly through neutral beam injection [1,2]. When TFTR finished operation in preparation for final shut down an aggressive three month campaign commenced for the purpose of recovering tritium inventory which was deposited on the internal surfaces of the > 80,000 liter volume vacuum vessel [3].…”

Section: Introductionmentioning

confidence: 99%

In-situ Tritium Measurements of the Tokamak Fusion Test Reactor Bumper Limiter Tiles Post D-T Operations

Gentile¹,

Skinner²,

Young³

et al. 1999

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-The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with members of the Japan Atomic Energy Research Institute (JAERI), TritiumEngineering Laboratory have commenced in-situ tritium measurements of the TFTR bumper limiter. The Tokamak Fusion Test Reactor (TFTR) operated with tritium from 1993 to 1997. During this time ~ 53,000 Ci of tritium was injected into the TFTR vacuum vessel. After the cessation of TFTR plasma operations in April 1997 an aggressive tritium cleanup campaign lasting ~ 3 months was initiated. The TFTR vacuum vessel was subjected to a regimen of glow discharge cleaning (GDC) and dry nitrogen and "moist air" purges. Currently ~ 7,500 Ci of tritium remains in the vacuum vessel largely contained in the limiter tiles. The TFTR limiter is composed of 1,920 carbon tiles with an average weight of ~ 600 grams each. The location and distribution of tritium on the TFTR carbon tiles are of considerable interest. Future magnetically confined fusion devices employing carbon as a limiter material may be considerably constrained due to potentially large tritium inventories being tenaciously held on the surface of the tiles.In-situ tritium measurements were conducted in TFTR bay L during August and November 1998. During the bay L measurement campaign open wall ion chambers and ultra thin thermoluminscent dosimeters (TLD) affixed to a boom and end effector were deployed into the vacuum vessel. The detectors were designed to make contact with the surface of the bumper limiter tile and to provide either real time (ion chamber) or passive (TLD) indication of the surface tritium concentration. The open wall ion chambers were positioned onto the surface of the tile in a manner which employed the surface of the tile as one of the walls of the chamber. The ion chambers, which are (electrically) gamma insensitive, were landed at four positions per tile. The geometry for landing the TLDÕs provided measurement at 24 positions per tile. The instrumentation was positioned on the tiles (96 tiles in each bay) by technicians who manipulated the boom and end effector from outside the vacuum vessel port. In addition to obtaining bay L tile measurements, 3 bumper limiter tiles were collected from the vacuum vessel for further analysis. During the bay L measurement campaign it was observed that several of the tiles in the lower third of the bumper limiter exhibited considerable surface flaking.

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Section: Introductionmentioning

confidence: 99%

In-situ Tritium Measurements of the Tokamak Fusion Test Reactor Bumper Limiter Tiles Post D-T Operations

Gentile¹,

Skinner²,

Young³

et al. 1999

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“…During this time the TFTR tritium systems processed ~ 1 Mega Curie of tritium, of which ~ 50, 000 Ci of tritium was supplied to the vacuum vessel through Neutral Beam Injection or by direct vessel gas injection [1]. At the completion of the TFTR D-T operational phase in April of 1997 the vacuum vessel was subject to a regimen of tritium cleanup operations which included vessel bake-out, deuterium Glow Discharge Cleaning, Helium / Oxygen Glow Discharge Cleaning, Pulse Discharge Cleaning, and moist air purges.…”

Section: Introductionmentioning

confidence: 99%

Visual tritium imaging of In-Vessel surfaces

Gentile¹,

Zweben²,

Skinner³

et al. 2000

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:A imaging detector has been developed for the purpose of providing a non-destructive, real time method of determining tritium concentrations on the surface of internal TFTR vacuum vessel components. The detector employs a green phosphor screen (P31, zinc sulfide: copper) with a wave length peak of 530 nm, a charge-coupled device (CCD) camera linked to a computer, and a detection chamber for inserting components recovered from the vacuum vessel. This detector is capable of determining tritium concentrations on the surfaces. The detector provides a method of imaging tritium deposition on the surfaces in a fairly rapid fashion.

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