Optimization of beryllium for fusion blanket applications
- 1. Argonne National Lab., IL (United States). Fusion Power Program
Description
The primary function of beryllium in a fusion reactor blanket is neutron multiplication to enhance tritium breeding. However, because heat, tritium and helium will be generated in and/or transported through beryllium and because the beryllium is in contact with other blanket materials, the thermal, mechanical, tritium/helium and compatibility properties of beryllium are important in blanket design. In particular, tritium retention during normal operation and release during overheating events are safety concerns. Accommodating beryllium thermal expansion and helium-induced swelling are important issues in ensuring adequate lifetime of the structural components adjacent to the beryllium. Likewise, chemical/metallurgical interactions between beryllium and structural components need to be considered in lifetime analysis. Under accident conditions the chemical interaction between beryllium and coolant and breeding materials may also become important. The performance of beryllium in fusion blanket applications depends on fabrication variables and operational parameters. First the properties database is reviewed to determine the state of knowledge of beryllium performance as a function of these variables. Several design calculations are then performed to indicate ranges of fabrication and operation variables that lead to optimum beryllium performance. Finally, areas for database expansion and improvement are highlighted based on the properties survey and the design sensitivity studies
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95004637; NTIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- ANL--EP/VU-84771
Conference
- Title
- Workshop on beryllium for fusion applications.
- Dates
- 4-5 Oct 1993.
- Place
- Karlsruhe (Germany).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26043695
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM; BREEDING BLANKETS; BREEDING RATIO; DESIGN; INFORMATION SYSTEMS; INTERSTITIAL HELIUM GENERATION; MATERIALS; MECHANICAL PROPERTIES; PERFORMANCE; PHYSICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; THERMONUCLEAR REACTORS; TRITIUM; TRITIUM RECOVERY
- Descriptors DEC
- ALKALINE EARTH METALS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CONVERSION RATIO; ELEMENTS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; METALS; NUCLEI; ODD-EVEN NUCLEI; RADIATION EFFECTS; RADIOISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-9310182--2-Vugraphs.