Breeding blanket

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The tritium breeding blanket (also known as a fusion blanket, lithium blanket or simply blanket), is a key part of many proposed fusion reactor designs. It serves several purposes; one is to act as a cooling mechanism, absorbing the energy from the neutrons produced within the plasma by the nuclear fusion reaction between deuterium and tritium (D-T), another is to "breed" further tritium fuel, that would otherwise be difficult to obtain in sufficient quantities, through the reaction of neutrons with lithium in the blanket.[1] The breeder blanket further serves as shielding, preventing the high-energy neutrons from escaping to the area outside the reactor and protecting the more radiation-susceptible portions, like the superconducting magnets, from damage.

Of these three duties, it is only the breeding portion that cannot be replaced by other means. For instance, a large quantity of water makes an excellent cooling system and neutron shield, as in the case of a conventional nuclear reactor. However, tritium is difficult to obtain in sufficient quantity to run a reactor through other means, so if commercial fusion using the D-T cycle is to be achieved, successful breeding of the tritium in commercial quantities is a requirement.

Breeding blanket designs are mostly based on lithium containing ceramics, with a focus on lithium titanate and lithium orthosilicate.[2] These materials, mostly in a pebble form, are used to produce and extract tritium and helium, must withstand high mechanical and thermal loads and should not become radioactive upon completion of their useful service life.

To date, no large-scale breeding system has been attempted, and it is an open question whether such a system is possible to create.

ITER runs a major effort in blanket design and will test a number of potential solutions.[3] Concepts for the breeder blanket include helium-cooled lithium lead (HCLL), helium-cooled pebble bed (HCPB), and water-cooled lithium lead (WCLL) methods.[4] Six different tritium breeding systems, known as Test Blanket Modules (TBM) wil be tested in ITER.[5]

References[]

  1. ^ "Tritium" (PDF). FAS/DoD. Retrieved 2021-11-30.
  2. ^ Lithium breeder ceramics Journal of the European Ceramic Society
  3. ^ "What is ITER?". ITER. Retrieved 2021-09-14.
  4. ^ Federici, G.; Boccaccini, L.; Cismondi, F.; Gasparotto, M.; Poitevin, Y.; Ricapito, I. (2019-04-01). "An Overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort". Fusion Engineering and Design. Amsterdam, Netherlands: Elsevier. 141: 30–42. doi:10.1016/j.fusengdes.2019.01.141.
  5. ^ Giancarli, Luciano (2016-11-07). "Committee Reviews Progress on Test Blanket Modules". ITER Newsline. St. Paul-lez-Durance, France: ITER. Retrieved 2021-03-20.

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