Review of the ITER Fuel Cycle · Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 15 Conclusions and Summary •ITER Fuel Cycle systems constitute a
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Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 1
David BabineauDavid BabineauITER Fuel Cycle Engineering Division ITER Fuel Cycle Engineering Division
Tritium Plant SectionTritium Plant Section
AndAnd
M. GluglaM. Glugla11, S. Maruyama, S. Maruyama11, R. Pearce, R. Pearce11, Li Bo, Li Bo22, B. Rogers, B. Rogers33, S. Willms, S. Willms44, , G. PiazzaG. Piazza55, T. Yamanishi, T. Yamanishi66, S. H. Yun, S. H. Yun7, 7, L. WorthL. Worth11 and W. Shuand W. Shu11
11ITER Organization, Cadarache, FranceITER Organization, Cadarache, France, , 22Southwest Institute of Physics, Chengdu, ChinaSouthwest Institute of Physics, Chengdu, China, , 33Savannah Savannah River National Laboratory, Aiken, SC USARiver National Laboratory, Aiken, SC USA, , 44Los Alamos National Laboratory, Los Alamos, NM, USALos Alamos National Laboratory, Los Alamos, NM, USA, , 55Fusion for Energy, Barcelona, SpainFusion for Energy, Barcelona, Spain, , 66JAEA, Directorates of Fusion Energy Research, ShirakataJAEA, Directorates of Fusion Energy Research, Shirakata--Shirane, Shirane, Tokai, Ibaraki, JapanTokai, Ibaraki, Japan, , 77National Fusion Research Institute, Daejeon, KoreaNational Fusion Research Institute, Daejeon, Korea
Review of the ITER Fuel CycleReview of the ITER Fuel Cycle
Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 5
Select Fuel Cycle Requirements• Fuelling rates and torus pumping requirements different for inductive (450 s), for hybrid (1000 s) or for steady state (3000 s) operation
– 200 Pam3s-1 D-T, 160 Pam3s-1 D-T, 120 Pam3s-1 D-T, respectively• Tritium flow rate up to 50% of nominal fuelling rate (tritium purity 90%) • Deuterium flow rate up to 100% of nominal fuelling rate• Peak flow rate for both deuterium & tritium up to 200% of nominal fuelling rate
• Fuelling system transfer lines operated at sub-atmospheric pressures– Reliable confinement of tritium in transfer lines
• Line breach can be detected by a pressure rise• Pressure drop in pressurized line could have been leak or increasing demand
Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 6
Selected Fuel Cycle Requirements (cont.)• Widely distributed Vacuum Systems
– Cryo-Pumps, Roughing Pumps and Leak Detection / Localization• Service vacuum system, diagnostics, cryogenic guard vacuum
– Transfer of gases to Tritium Plant for processing• Tritium Plant for storage, supply, gas processing, isotope separation, tritium confinement / controlled discharge
– Safe and secured operation of hydrogen isotope inventories• Tritium accountancy and tracking
– Minimization of effluents and releases – 0.6 gram/year licensed (222 TBq = 6000 curies = 2.2 LiterSTP T2 )
• Ventilation 300 x 103 m3/hour – 2.63 x 1012 Liters per year
Review of the ITER Fuel Cycle Systems David Babineau, 23rd IAEA FEC, 2010. Page 9
Tritium Confinement for ITER Nuclear Buildings • Confinement of tritium within Fuel Cycle processing systems and components is the most important safety objective
– Basic targets of confinement• Prevent spreading of radioactive material in normal operation• Keep radiological consequences in off-normal conditions within acceptable
levels– Confinement function is achieved by a coherent set of physical barriersand / or auxiliary techniques
• First confinement system designed to prevent releases of radioactive materials into the accessible working areas
• Second confinement system prevents releasesto general public and the environment
– ISO 17873 provides criteria for design & operation of ventilation systems (HVAC) for nuclear installations other than nuclear reactors
• ISO 17873 was transposed for ITER to include gaseous tritium and tritiated compounds as airborne contaminants