Published 1979
| Version v1
Report
Restricted
Fission gas behavior in mixed-oxide fuel during transient overpower
Description
Fission gas behavior can be important in determining fuel pin and core performance during a reactor transient. The results are presented of examinations characterizing the changes in microstructural distribution and retention of fission gas in fuel for a series of transient overpower (50 cents/s) tested mixed-oxide fuel pins and their steady state siblings
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- HEDL-SA--1747-FD
Conference
- Title
- International meeting on fast reactor safety technology.
- Dates
- 19 - 23 Aug 1979.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11541320
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; LMFBR TYPE REACTORS; MICROSTRUCTURE; PLUTONIUM DIOXIDE; REACTOR CORE DISRUPTION; REACTOR SAFETY; SPATIAL DISTRIBUTION; TRANSIENT OVERPOWER ACCIDENTS; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; CRYSTAL STRUCTURE; DISTRIBUTION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR ACCIDENTS; REACTORS; SAFETY; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- CONF-790816--86.