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This presentation by Scott Willms from Los Alamos National Laboratory discusses the essential needs for tritium processing and control in the US ITER Test Blanket Module (TBM). It covers the safety concerns surrounding tritium handling, the characterization of TBM performance, and various tritium extraction concepts from both PbLi and He systems. Key topics include tritium migration, vacuum permeator designs, and the challenges associated with extracting tritium under ITER and DEMO scenarios. The talk highlights the importance of advanced research and development to establish effective tritium handling systems.
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Potential Tritium Processing/Control Needs for US ITER TBM Scott Willms Los Alamos National Laboratory Presented at INL August 11, 2005
Overarching drivers • Must handle tritium in TBM properly • For safety concerns • To accurately characterize TBM performance • In addition TBM will be a unique opportunity • To develop and demonstrate tritium extraction concepts • To characterize tritium migration • To test tritium containment technologies • Time phasing • Non-ITER, non-tritium testing • ITER year 1-10 tests • ITER year 11-20 tests • DEMO
Tritium process overview Recover tritium from He Tritium control important throughout Also use as test station Use He to strip T from PbLi PbLi loop He loop T permeation thru HX tubes Recover tritium from He Avg. T2 breeding rate: 0.024 sccm He loop
Summary of tritium processing concepts for DCLL-Extraction of tritium from PbLi • Vacuum permeator with Ta or Nb membrane (bare or coated) • Vacuum permeator with Pd or Pd alloy membrane • Vacuum permeator with ferritic steel membrane • Bubble column • Vacuum disengager • Getter • Use heat exchanger to transfer tritium to He and subsequently separate T from He.
Summary of tritium processing concepts for DCLL-Extraction of tritium from He • Vacuum permeator with Pd alloy membrane • Vacuum permeator with Ta or Nb membrane (bare or coated) • Oxidation/adsorption of tritium in He at elevated temperatures • Cryogenic molecular sieve
Issues associated with tritium extraction from He (DCLL and Ceramic Blanket)
T, O, PbLi, wall system • Tritium from PbLi to wall • Don’t know • PbLi + T(l) <-> Wall + T(s) • So currently work around with • PbLi + T(l) <-> T2(g) • T2(g) <-> Wall + T(s) • Gives answer, but there is no T2(g) • Need real experiment • Also, what is the fate of T and O in PbLi? • If T turns into water, permeation will be very different • Does not appear water will form, but an experiment is needed
Highest priority topics • Further systems modeling needed • Tritium processing • Tritium migration • Extraction from PbLi • Tritium mass transfer coefficients in PbLi • Bubbler design evaluation • Bubbler data • Vacuum permeator • Extraction from He • Vacuum permeator • Fate of tritium in PbLi • LiH, Li with H2 in solution, Li with H+? • Mechanism/rate of H transport into wall • Tritium migration • Permeation barrier modeling and experiments
Next steps • Establish a baseline set of R&D • Prepare project information for R&D (scope/schedule/budget)