Difusion of tritium, generated in lithium methanetitanate LI2TIO3 in process of warm neutron radiation in WWRK reactor

Authors

  • A.A. Kuykabayeva Al-Farabi Kazakh National University, Kazakstan, Almaty
  • I.N. Bekman Lomonosov Moscow State University, Moscow, Russia
  • I.M. Buntseva Lomonosov Moscow State University, Moscow, Russia
  • I.L. Tazhibayeva IAE NNC RK, Kurchatov, Kazakhstan
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Keywords:

fusion reactor, blanket, tritium generation, tritium diffusion, lithium ceramics, neutron irradiation, radiation defects

Abstract

Automation and processing software was developed for interpretation of the results of reactor experiments on tritium release study. Tritium was continuously generated as a result of nuclear reaction of lithium-6 and thermal neutrons under variable thermal impacts on lithium metatitanate. Main gas release parameters, which are necessary for assessment of applicability to use the lithium titanate granules in tritium blankets, were calculated: tritium retention/release ratio, retention time, activation energy of HT thermodesorption, activation energy of T+ bulk diffusion, and corresponding pre-exponential (frequency) factors. It was shown that tritium diffusion coefficient was actively increasing during first 10 months of reactor irradiation of lithium metatitanate, then effective diffusion coefficient stabilized at the value of 1.3×10-7 cm2/s and afterwards the coefficient didn’t change or changed insignificantly.

References

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Published

2013-09-27

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Section

Theoretical Physics. Nuclear and Elementary Particle Physics. Astrophysics