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							     Overview of the
Safety and Tritium Applied
 Research (STAR) Facility
               Phil Sharpe
         Fusion Safety Program
     Idaho National Laboratory, USA

          HAPL Program Meeting
                  ORNL
            21-22 March 2006
                                                                 Fusion Safety Program



           STAR Mission and Research
•   Provide laboratory infrastructure to study tritium science and technology
    issues associated with the development of safe and environmentally friendly
    fusion energy
•   Designated a National User Facility
•   Research thrust areas
     – Plasma-material interactions of PFC materials with energetic tritium and
       deuterium ions
     – Fusion safety: chemical reactivity, activation product mobilization and
       dust/debris characterization for PFC materials; tritium behavior in fusion
       systems (in-vessel source term)
     – Molten salts and fusion liquids for tritium breeder and coolant applications
     – Fission reactor tritium production permeation issues; AGR fuel tritium
       retention and release studies
     – Tritium plant and fuel cycle issues for MFE and IFE




                                                                                      Slide 1
                                                                                  Fusion Safety Program
                                    STAR Floor-plan Layout
   Glovebox
                                                                                  Chemical reactivity
    TCS         Tritium       Tritium                                               experiment
                 SAS       Stack monitor



                                               D ion implantation
                                                 experiment

Glovebox exhaust
   manifold
                          Tritium Plasma Exp                         Flibe preparation
                                                                    purification & testing




Flibe-tritium
experiment                                                           Flibe Salt
                                                                     2Lif-BeF2




 Flibe-corrosion                                    15,000 Ci tritium limit
                                                   15,000 Ci tritium limit
 experiment                                         Segregation of operations
                                                   Segregation of operations/ventilation
                                                   Once-through room ventilation
                                                    Gloveboxes and hoods
                                                   Gloveboxes and hoods
                                                    Tritium cleanup system
                                                   Tritium cleanup system (TCS)
                                                   Tritium storage and assay system (SAS)
                                                    Once-through room ventilation
                                                                                                        Slide 2
                                                              Fusion Safety Program
                            Key systems in STAR




                                     Molten Salt Tritium
                                     Behavior Experiment   Tritium
Tritium Plasma Experiment                                  Storage and
and Enclosure                                              Assay
                                                           System




                                                               Steam and air
                                Molten Salt Preparation,       chemical reactivity
Tritium Cleanup System          Purification, and REDOX        test apparatus
                                Experiments                                          Slide 3
                                                     Fusion Safety Program

  Star Tritium Storage and Assay System
Handles reception, distribution, and accountability of tritium inventory




  SAS glovebox Setup                  SAS manifold and vacuum pumps
                                                                       Slide 4
                                                         Fusion Safety Program

   STAR Tritium Cleanup System (TCS)
Removes tritium in process gases from glovebox atmospheres and
experiment systems.
               Outlet IC             Inlet

                                             Inlet sample loop
  Condenser                                  Control

                                    Heat exchanger
   MS water

                                Mole sieve bed

               Blower

                            Catalyst beds




                                                                           Slide 5
                                                 Fusion Safety Program



    Highlights of Recent Accomplishments
•    Useable tritium inventory now 1300 Ci
        –   300 Ci in equimolar H2:D2:T2 calibration standard
        –   1000 Ci T2 available for experiments
        –   shipments from SRS limited to 1000 Ci with standard
            TYPE-A shipping container




              Shipping Vessel (1 available)




                                                                   Slide 6
                                                                                                                                             Fusion Safety Program


Highlights of Recent Accomplishments, cont.
• TPE Operations Initiated
                                  –            plasma characteristics testing and diagnostics installation
                                               are present focus
                                               peaks.out 10:56:12 AM 1/2/06
                                      REGION 1                             REGION 2
                          Filament Heat-up                         Plasma Operation
                   10-3   (0-250 Amps in 50 Amp increments)        (4 periods of testing)



                   10-4
 Pressure (Torr)




                   10-5




                   10-6




                   10-7

                                 H2     N2
                                 H2O    O2

                   10-8
                          3000         4000       5000
                                                     Time (sec.)
                                                                   6000         7000        8000
                                                                                                   low intensity plasma (<0.05 A/cm 2)   moderate intensity plasma (~ 0.2 A/cm 2)
                      chamber gas species during first plasma

                                  –            materials testing with D2 to start early April (W and Mo)
                                  –            T2 components upgrade and tests to be completed in June,
                                               including plasma operation
                                  –            materials testing with D2/T2 to start mid-July (W and Mo, Be testing
                                               will start in September)

                                                                                                                                                                            Slide 7
                                                        Fusion Safety Program


STAR is Ready for Operation of Tritium Experiments
                    Plans for the CY 2006:
• Molten Salt Tritium Permeation Experiment:
   –   100 to 300 Ci transferred as D2/T2 in vessel loaded with SAS
   –   experiment will be setup in glovebox used for previous permeation
       studies
   –   diagnostics to include QMS, gas chromatograph, on-line ion chamber,
       and catalytic recovery
   –   effluent will exhaust via facility stack


• TPE Tritium Experiments:
   –   700 to 900 Ci transferred as T2 in vessel loaded with SAS
   –   further blending in TPE for desired T ion flux
   –   TDS measurements following plasma exposure will indicate retained D
       and T
   –   local U-Bed capture in TPE; effluent routed to TCS for complete
       cleanup

                                                                          Slide 8

						
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