Published 1993
| Version v1
Book
Evaluation of inelastic strain in elevated temperature components
Creators
- 1. Fuji Electric Co., Ltd., Kawasaki (Japan)
- 2. Japan Atomic Power Co., Tokyo (Japan)
- 3. FBR Engineering Co., Ltd., Tokyo (Japan)
- 4. Mitsubishi Heavy Ind., Ltd., Kobe (Japan)
- 5. Toshiba Corp., Yokohama (Japan)
- 6. Hitachi, Ltd., Ibaraki (Japan)
- 7. Kawasaki Heavy Industries, Ltd., Tokyo (Japan)
Description
The elevated temperature design guide for Japanese Demonstration Fast Breeder Reactor (DFBR) called DDS has been studied on the basis of the design guide for Monju plant reflecting recent test results and analyses. This paper describes the whole concept of evaluation of accumulated inelastic strains, including treating method of secondary membrane stresses in the evaluation of enhanced creep strain and plastic ratcheting strain which were extended the O'Donnell's method to ratcheting region based on biaxial model and finite element method analyses
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0989-7
- Imprint Title
- High-temperature service and time dependent failure
- Imprint Pagination
- 231 p.
- Journal Page Range
- p. 19-25.
Conference
- Title
- 1993 pressure vessel and piping conference.
- Dates
- 25-29 Jul 1993.
- Place
- Denver, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25026049
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; CREEP; ELASTICITY; FBR TYPE REACTORS; FINITE ELEMENT METHOD; JAPAN; MECHANICAL PROPERTIES; MONJU REACTOR; PLASTICITY; RATCHETING; REACTOR COMPONENTS; STRAINS; STRESSES
- Descriptors DEC
- ASIA; BREEDER REACTORS; CALCULATION METHODS; DEFORMATION; DEVELOPED COUNTRIES; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-930702--Vol.262.