Published February 1985
| Version v1
Journal article
High-temperature-structural design and research and development for reactor system components
Description
The design of reactor system components requires high-temperature-structural design guide with the consideration of the creep effect of materials related to research and development on structural design. The high-temperature-structural design guideline for the fast prototype reactor MONJU has been developed under the active leadership by Power Reactor and Nuclear Fuel Development Corporation and Toshiba has actively participated to this work with responsibility on in-vessel components, performing research and development programs. This paper reports the current status of high-temperature-structural-design-oriented research and development programs and development of analytical system including stress-evaluation program. (author)
Additional details
Publishing Information
- Journal Title
- Toshiba Rebyu
- Journal Volume
- 40
- Journal Issue
- 2
- Series
- Toshiba Rebyu.
- Journal Page Range
- 131-134
- ISSN
- 0372-0462
- CODEN
- TORBA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 17019813
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; CREEP; FATIGUE; HEAT TRANSFER; HIGH TEMPERATURE; HYDRAULICS; MATERIALS TESTING; MONJU REACTOR; REACTOR COMPONENTS; STRUCTURAL MODELS; THERMAL STRESSES; THERMODYNAMICS
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; STRESSES; TESTING