Engineering problems of the fusion breeder Metadata
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Title
- Main Title Engineering problems of the fusion breeder
Creator
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Author: Moir, R. W.Creator Type: Personal
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Author: Lee, J. D.Creator Type: Personal
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Author: Barr, W. L.Creator Type: Personal
Publisher
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Name: Lawrence Livermore National LaboratoryPlace of Publication: [Livermore,] California
Date
- Creation: 1981-10-22
Language
- English
Description
- Content Description: A study of fission suppressed blankets for the tandem mirror not only showed such blankets to be feasible but also to be safer than fissioning blankets. Such hybrids could produce enough fissile material to support up to 17 light water reactors of the same nuclear power rating. Beryllium was compared to /sup 7/Li for neutron multiplication; both were considered feasible but the blanket with Li produced 20% less fissile fuel per unit of nuclear power in the reactor. The beryllium resource, while possibly being too small for extensive pure fusion application, would be adequate (with carefully planned industrial expansion) for the hybrid because of the large support ratio, and hence few hybrids required. Radiation damage and coatings for beryllium remain issues to be resolved by further study and experimentation. Molten salt reprocessing was compared to aqueous solution reprocessing (thorex). The molten salt reprocessing cost is $3.4/g fissile, whereas aqueous reprocessing cost $24 or $43/g for the thorium metal or oxide fuel form.
- Physical Description: 7 pages
Subject
- Keyword: Elements
- Keyword: Hybrid Reactors
- STI Subject Categories: 70 Plasma Physics And Fusion Technology
- Keyword: Light Nuclei
- Keyword: Reactor Components
- Keyword: Alkali Metal Isotopes
- Keyword: Isotopes
- Keyword: Separation Processes
- Keyword: Lithium Isotopes
- Keyword: Odd-Even Nuclei
- Keyword: Nuclei
- Keyword: Lithium 7
- Keyword: Reprocessing
- Keyword: Metals
- Keyword: Cost
- Keyword: Engineering
- Keyword: Magnetic Mirror Type Reactors
- Keyword: Alkaline Earth Metals
- Keyword: Tmr Reactors
- Keyword: Breeding Blankets
- Keyword: Thermonuclear Reactors 700201* -- Fusion Power Plant Technology-- Blanket Engineering
- Keyword: Stable Isotopes
- Keyword: Beryllium
Source
- Conference: 9. symposium on engineering problems of fusion research, Chicago, IL, USA, 26 Oct 1981
Collection
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Name: Office of Scientific & Technical Information Technical ReportsCode: OSTI
Institution
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Name: UNT Libraries Government Documents DepartmentCode: UNTGD
Resource Type
- Article
Format
- Text
Identifier
- Other: DE82002580
- Report No.: UCRL-86040
- Report No.: CONF-811040-62
- Grant Number: W-7405-ENG-48
- Office of Scientific & Technical Information Report Number: 6131194
- Archival Resource Key: ark:/67531/metadc1113830
Note
- Display Note: NTIS, PC A02/MF A01.