Guidelines established for the structural design of the experimental fast reactor JOYO
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
Description
Compared with light-water reactors, sodium-cooled fast reactors operate at higher temperature and lower pressure. Thus, high thermal stresses are induced in the structural components at steady as well as transient operation, while mechanical stresses due to internal pressure are comparatively low. The materials used for the structural components exposed to sodium are liable to creep under the stress, while the mechanical properties are further impaired by mass transfer in hot sodium circuits. Sodium-cooled fast reactors also differ radically in the principles that govern safety considerations and the composition of the coolant system the design critaria of the components of such reactors are largely governed by these safety considerations and by the particularities of the coolant system. The guidelines established for the structural design of JOYO have involved these new problems which applied to all the sodium coolant system pressure boundaries including the core support structure. An outline is give of the guidelines established for the design. (author)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.14.678Additional details
Additional titles
- Original title (Japanese)
- 高速実験炉「常陽」のナトリウム機器構造設計指針
Identifiers
- DOI
- 10.3327/jaesj.14.678;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 14
- Journal Issue
- 12
- Journal Page Range
- p. 678-693
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53100612
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLANTS; CORROSION; CREEP; FATIGUE; JOYO REACTOR; MECHANICAL STRUCTURES; PLANNING; PRESSURE DEPENDENCE; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RECOMMENDATIONS; SODIUM; SPECIFICATIONS; TEMPERATURE RANGE 0400-1000 K; THERMAL STRESSES; TRANSIENTS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; CHEMICAL REACTIONS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MECHANICAL PROPERTIES; METALS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STRESSES; TEMPERATURE RANGE
Optional Information
- Notes
- 5285200; This record replaces 04065744