Published 1981
| Version v1
Report
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Preirradiation microstructural characterization of FFTF mixed oxide fuel
Description
Charts, drawings, graphs, and photographs are presented concerning the research program to evaluate potential for fuel to undergo densification during irradiation, to assure PuO2 homogeneity in mixed oxide fuel, to provide data base for pre-/post-irradiation comparisons, and to evaluate effect of fuel fabrication conditions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 as DE82011168.Files
17010154.pdf
Files
(2.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 39 p.
- Report number
- HEDL-SA--2294-FP
Conference
- Title
- ANS winter meeting.
- Dates
- 29 Nov - 4 Dec 1981.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17010154
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FABRICATION; FFTF REACTOR; FUEL PELLETS; FUEL RODS; MICROSTRUCTURE; PLUTONIUM DIOXIDE; POWDER METALLURGY; QUALITY CONTROL; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CONTROL; CRYSTAL STRUCTURE; EPITHERMAL REACTORS; FAST REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; METALLURGY; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- CONF-811103--112.