Published 1989
| Version v1
Book
Super Phenix fuel storage tank investigations concerning the sodium leak
Creators
- 1. Novatome Industries, 92 - Le Plessis-Robinson (France)
Description
Following the detection of a sodium leak from the fuel storage drum of the Super Phenix LMFBR reactor, investigations have been undertaken in order to: check again that the design of the storage main vessel was right, make an assessment of the vessel behavior under the actual loadings supported during its two first years of life, check the mechanical properties of materials (in purchase and present conditions), find whether the leak could be explained by design failure or unexpected material properties
Additional details
Additional titles
- Subtitle (English)
- Dimensionnal and material aspects
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 323 p.
- Series
- Volume E. Fast reactor core and coolant circuit structures.
- Journal Page Range
- p. 73-78.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21080258
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DYNAMIC LOADS; LEAK TESTING; MECHANICAL PROPERTIES; REACTOR CORE RESTRAINTS; REACTOR MATERIALS; REACTOR SAFETY EXPERIMENTS; REACTOR VESSELS; SPECIFICATIONS; SUPER PHENIX REACTOR
- Descriptors DEC
- BREEDER REACTORS; CONTAINERS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; PLUTONIUM REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; RESTRAINTS; SODIUM COOLED REACTORS; TESTING
Optional Information
- Secondary number(s)
- CONF-890855--.