Fast flux test facility core restraint system performance
Description
The characterizing of the Fast Flux Test Facility (FFTF) core restraint system performance has been ongoing since the first operating cycle. The characterization consists of prerun analysis for each core load, in-reactor and postirradiation measurements of subassembly withdrawal loads and deformations, and using measurement data to fine tune predictive models. Monitoring FFTF operations and performing trend analysis has made it possible to gain insight into core restraint system performance and head off refueling difficulties while maximizing component lifetimes. Additionally, valuable information for improved designs and operating methods has been obtained. The focus is on past operating experience, emphasizing performance improvements and avoidance of potential problems. (author)
Additional details
Additional titles
- Augmented title (English)
- Reactor core restraints
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (United Kingdom)
- ISBN
- 0 7277 1566 6
- Imprint Title
- Fast reactor core and fuel structural behaviour
- Imprint Pagination
- 326 p.
- Journal Page Range
- p. 275-282.
Conference
- Title
- International conference on fast reactor core and fuel structural behaviour.
- Dates
- 4-6 Jun 1990.
- Place
- Inverness (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 23049280
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFORMATION; DESIGN; FFTF REACTOR; PERFORMANCE; POST-IRRADIATION EXAMINATION; REACTOR CORE RESTRAINTS; REACTOR FUELING
- Descriptors DEC
- EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; RESTRAINTS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS