Tritium inventory control—the experience with DT tokamaks and its relevance for future machines

Bell, A.C.; Gentile, C.; Lässer, R.; Coad, J. P.

doi:10.1016/s0920-3796(03)00137-6

Cited by 13 publications

(6 citation statements)

References 17 publications

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“…Cooling water has leaked into vacuum systems (Surle, 1998) but it can be removed by glow discharge and baking (Pearce, 2001). Bell (2003) noted that some sulfur hexafluoride gas used in neutral beam injectors leaked into the vacuum vessel of the JET machine. This gas was unwelcome in the tritium cleanup system but apparently did not pose a concern for the vacuum components despite the fluorine halogen in that chemical compound.…”

Section: Flow and Flow Mediamentioning

confidence: 99%

“…Often, the chlorides are an impurity in the process fluid, but ITER fluids should have very low chloride content. However, it is known that fluorides have been an impurity in tokamaks due to the use of sulfur hexafluoride electrical insulation gas (Bell, 2003); fortunately these leaks have not caused any concerns with stainless steel corrosion. A possible countermeasure for fluoride corrosion is the use of a trap (Viola, 1992).…”

Section: Failure Rate Calculation For Vacuum Pipingmentioning

confidence: 99%

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Vacuum Bellows, Vacuum Piping, Cryogenic Break, and Copper Joint Failure Rate Estimates for ITER Design Use

Cadwallader¹

2010

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Section: Flow and Flow Mediamentioning

confidence: 99%

Section: Failure Rate Calculation For Vacuum Pipingmentioning

confidence: 99%

Vacuum Bellows, Vacuum Piping, Cryogenic Break, and Copper Joint Failure Rate Estimates for ITER Design Use

Cadwallader¹

2010

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“…Concerning the exposure of the workers to ionising radiation, studies have been done since the first experiments involving tritium (for example [8][9][10]). JET policy has been to sample all persons with access to tritium handling areas.…”

Section: D-t Jet Experimentsmentioning

confidence: 99%

Tritium and workers in fusion devices—lessons learnt

Rodrı́guez-Rodrigo¹,

Elbez-Uzan²,

Alejaldre³

2009

J. Radiol. Prot.

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Fusion machines from all over the world have contributed to the knowledge accumulated in fusion science. This knowledge has been applied to design new experimental fusion machines and in particular ITER. Only two fusion devices based on magnetic confinement have used deuterium and tritium fuels to-date-the Tokamak Fusion Test Reactor, TFTR, in Princeton, USA, and JET, the European tokamak. These machines have demonstrated that the fusion reaction is achievable with these fuels, and have provided valuable lessons on radioprotection-related issues as concerns tritium and workers. Dedicated tritium installations for fusion research and development have also contributed to this knowledge base.

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“…The relevant features of the procedures implemented at JET for tritium inventory control, where a shot-byshot approach was, will be adopted for ITER [1,2] ITER than on existing tokamaks due to the higher (by orders of magnitude) fuelling rates and pulse lengths, and the significant uncertainties as to the fraction of tritium which will be retained on/in PFC's. With the reference ITER fuelling rate of 120 Pa m 3 /s of 50/50% DT (corresponding to ∼0.16 g/s of tritium), the PFC limit (330 g) would be reached in approximately 40,000 s of accumulated pulse duration, equivalent to ∼15 long or 100 short pulses, assuming 5% retention.…”

Section: Introductionmentioning

confidence: 99%