Integration of the tritium purification system (TPS) into TFTR operations

S. Raftopoulos, R. Scillia, P. Sichta, L. Dudek, G. Labik, J. Satkofsky, J. Langford, D. Voorhees

Research output: Contribution to conferencePaperpeer-review

2 Scopus citations

Abstract

The TPS is a hydrogen isotope separation system put into operation within the Tokamak Fusion Test Reactor (TFTR) Tritium Systems. The TPS extracts and purifies tritium from TFTR plasma exhausts, then returns it for reuse as plasma fueling. The TPS operates in two stages: Separation of hydrogen isotopes from the TFTR plasma waste effluents via a Palladium/Silver diffuser; and separation of hydrogen isotopes via a multi-stage cryogenic distillation system. TPS interfaces with the Gas Holding Tanks (GHTs), the Torus Cleanup System (TCS), the plant stack via the Tritiated Vent System, the Tritium Storage and Delivery System, and the Tritium Storage and Delivery Cleanup System (TSDCS). Commissioning of TPS included: Operational testing at CFFTP and at Princeton, thorough helium and tritium leakchecks, trial run with a limited tritium inventory (1000 Ci), and a 10,000 Ci integrated systems test.

Original languageEnglish (US)
Pages581-584
Number of pages4
StatePublished - 1995
EventProceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - Champaign, IL, USA
Duration: Oct 1 1995Oct 5 1995

Conference

ConferenceProceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)
CityChampaign, IL, USA
Period10/1/9510/5/95

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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