• DocumentCode
    325001
  • Title

    Tritium reduction and control in the vacuum vessel during TFTR outage and decommissioning

  • Author

    Blanchard, W. ; Camp, R. ; Carnevale, H. ; Casey, M. ; Llins, J. ; Gentile, C.A. ; Gibson, M. ; Hosea, J.C. ; Kalish, M. ; Langford, J. ; Langish, S. ; Miller, D. ; Nagy, A. ; Pearson, G.G. ; Raucci, R. ; Rule, K. ; Winston, J.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • Volume
    1
  • fYear
    1997
  • fDate
    6-10 Oct 1997
  • Firstpage
    297
  • Abstract
    In the summer/fall of 1996 after nearly three years of D-T operations, TFTR underwent an extended outage during which large port covers were removed from the vacuum vessel in order to complete upgrades to the tokamak. Following the venting of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium in the vacuum vessel so as to minimize the exposure to personnel during port cover removal and reinstallation. The first phase of the program to reduce the free tritium consisted of direct flowthrough of room air through the vacuum vessel to the molecular sieve beds using the Torus Cleanup System. Real time measurements of the effluent tritium concentration were used to derive the amount of tritium removed from the torus. Once the free tritium in the vessel had been reduced to approximately 50 Ci, a second phase was initiated using a 55 Gallon Drum Bubbler System for the direct processing of the vacuum vessel to further lower the tritium level in the torus. Tritium oxide is absorbed by the bubbler system with the exhaust vented to one of the tritium monitored HVAC ventilation stacks. To preclude the release of tritium to the Test Cell location of TFTR and to minimize the exposure of workers, a variable flow exhaust system was employed in order to maintain a negative pressure in the vacuum vessel between 0.05" and 1.5" w.c. during the removal of port covers ranging in size from approximately 5 to 1000 in2. These systems were completely successful in reducing and controlling the free tritium in TFTR and were instrumental in maintaining ALARA (As Low As Reasonably Achievable) exposures to tritium during the 1996 outage. These systems are again being utilized during the safe shutdown and decommissioning of TFTR which commenced in April of 1997. This paper describes in detail the configuration of these systems and the data obtained during the outage and sale shutdown of TFTR
  • Keywords
    fusion reactor safety; nuclear materials safeguards; tritium; 55 Gallon Drum Bubbler System; ALARA; As Low As Reasonably Achievable; D-T operations; HVAC ventilation stacks; TFTR outage; Torus Cleanup System; decommissioning; direct flowthrough; direct processing; effluent tritium concentration; free tritium; molecular sieve beds; personnel exposure; port cover removal; room air; three tier system; tokamak upgrades; torus venting; tritium control; tritium oxide absorption; tritium reduction; tritium release; vacuum vessel; variable flow exhaust system; Control systems; Effluents; Exhaust systems; Molecular sieves; Monitoring; Personnel; System testing; Tokamaks; Vacuum systems; Ventilation;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-4226-7
  • Type

    conf

  • DOI
    10.1109/FUSION.1997.687041
  • Filename
    687041