Breeding blanket: Difference between revisions
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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; |
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; primarily it is to produce (or "breed") further [[tritium]] fuel for the [[nuclear fusion]] reaction, which would otherwise be difficult to obtain in sufficient quantities, through the reaction of [[neutron]]s with [[lithium]] in the blanket.<ref>{{Cite web|title=Tritium|url=https://irp.fas.org/agency/dod/jason/tritium.pdf|access-date=2021-11-30|website=FAS/DoD|language=en}}</ref> The blanket may also act as a cooling mechanism, absorbing the energy from the neutrons produced by the reaction between [[deuterium]] and [[tritium]] ("[[Deuterium–tritium fusion|D-T]]"), and further serves as shielding, preventing the high-energy neutrons from escaping to the area outside the reactor and protecting the more radiation-susceptible portions, such as ohmic<!-- Helion Energy is using regular copper magnets, water cooled --> or [[superconductor|superconducting]] magnets, from damage. |
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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. |
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 not a naturally occuring resource, and thus 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. |
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| ⚫ | [[ITER]] runs a major effort in blanket design and will test a number of potential solutions.<ref>{{Cite web|title=What is ITER?|url=http://www.iter.org/proj/inafewlines|access-date=2021-09-14|website=ITER|language=en}}</ref> Concepts for the breeder blanket include helium-cooled lithium lead (HCLL), helium-cooled pebble bed (HCPB), and water-cooled lithium lead (WCLL) methods.<ref>{{cite journal |last1=Federici|first1=G.|last2=Boccaccini|first2=L.| last3=Cismondi|first3=F. |last4=Gasparotto|first4=M. | last5=Poitevin|first5=Y.| last6=Ricapito|first6=I. | title=An Overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort|journal=Fusion Engineering and Design|publisher=Elsevier |location=Amsterdam, Netherlands| date=2019-04-01 |volume=141|pages=30–42|doi=10.1016/j.fusengdes.2019.01.141|doi-access=free}}</ref> Six different tritium breeding systems, known as Test Blanket Modules (TBM) wil be tested in ITER.<ref>{{cite web |last=Giancarli|first=Luciano|title=Committee Reviews Progress on Test Blanket Modules|url= https://www.iter.org/newsline/-/2572| magazine=ITER Newsline |publisher=ITER|location=St. Paul-lez-Durance, France|date=2016-11-07| access-date=2021-03-20}}</ref> |
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| ⚫ | Some breeding blanket designs are based on lithium containing ceramics, with a focus on [[lithium titanate]] and [[lithium orthosilicate]].<ref>[https://hal.archives-ouvertes.fr/hal-02307643/document Lithium breeder ceramics] Journal of the European Ceramic Society</ref> 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 excessively radioactive upon completion of their useful service life. |
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To date, no large-scale breeding system has been attempted, and it is an open question whether such a system is possible to create. |
To date, no large-scale breeding system has been attempted, and it is an open question whether such a system is possible to create. |
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Since the DT reaction produces only one neutron, and the breeding process produces at most one tritium nucleus per neutron, unless the breeding were 100% efficient, breeding alone cannot produce all the tritium needed to fuel the reaction. |
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| ⚫ | [[ITER]] runs a major effort in blanket design and will test a number of potential solutions.<ref>{{Cite web|title=What is ITER?|url=http://www.iter.org/proj/inafewlines|access-date=2021-09-14|website=ITER|language=en}}</ref> Concepts for the breeder blanket include helium-cooled lithium lead (HCLL), helium-cooled pebble bed (HCPB), and water-cooled lithium lead (WCLL) methods.<ref>{{cite journal |last1=Federici|first1=G.|last2=Boccaccini|first2=L.| last3=Cismondi|first3=F. |last4=Gasparotto|first4=M. | last5=Poitevin|first5=Y.| last6=Ricapito|first6=I. | title=An Overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort|journal=Fusion Engineering and Design|publisher=Elsevier |location=Amsterdam, Netherlands| date=2019-04-01 |volume=141|pages=30–42|doi=10.1016/j.fusengdes.2019.01.141|doi-access=free}}</ref> Six different tritium breeding systems, known as Test Blanket Modules (TBM) wil be tested in ITER.<ref>{{cite web |last=Giancarli|first=Luciano|title=Committee Reviews Progress on Test Blanket Modules|url= https://www.iter.org/newsline/-/2572| magazine=ITER Newsline |publisher=ITER|location=St. Paul-lez-Durance, France|date=2016-11-07| access-date=2021-03-20}}</ref> |
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==References== |
==References== |
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Revision as of 01:17, 7 August 2023
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; primarily it is to produce (or "breed") further tritium fuel for the nuclear fusion reaction, which would otherwise be difficult to obtain in sufficient quantities, through the reaction of neutrons with lithium in the blanket.[1] The blanket may also act as a cooling mechanism, absorbing the energy from the neutrons produced by the reaction between deuterium and tritium ("D-T"), and further serves as shielding, preventing the high-energy neutrons from escaping to the area outside the reactor and protecting the more radiation-susceptible portions, such as ohmic or 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 not a naturally occuring resource, and thus 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.
ITER runs a major effort in blanket design and will test a number of potential solutions.[2] Concepts for the breeder blanket include helium-cooled lithium lead (HCLL), helium-cooled pebble bed (HCPB), and water-cooled lithium lead (WCLL) methods.[3] Six different tritium breeding systems, known as Test Blanket Modules (TBM) wil be tested in ITER.[4]
Some breeding blanket designs are based on lithium containing ceramics, with a focus on lithium titanate and lithium orthosilicate.[5] 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 excessively 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.
Since the DT reaction produces only one neutron, and the breeding process produces at most one tritium nucleus per neutron, unless the breeding were 100% efficient, breeding alone cannot produce all the tritium needed to fuel the reaction.
References
- ^ "Tritium" (PDF). FAS/DoD. Retrieved 2021-11-30.
- ^ "What is ITER?". ITER. Retrieved 2021-09-14.
- ^ 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. 141. Amsterdam, Netherlands: Elsevier: 30–42. doi:10.1016/j.fusengdes.2019.01.141.
- ^ Giancarli, Luciano (2016-11-07). "Committee Reviews Progress on Test Blanket Modules". ITER Newsline. St. Paul-lez-Durance, France: ITER. Retrieved 2021-03-20.
- ^ Lithium breeder ceramics Journal of the European Ceramic Society
External links
- "Tritium Breeding". ITER.
- Giancarli, Luciano (5 June 2017). "Tritium breeding systems enter preliminary design phase". ITER.