Published December 1992
| Version v1
Journal article
Recent achievements at PNC in the development of high temperature structural design methods for FBR components
- 1. Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corp., Narita, Ibaraki (Japan)
Description
The major achievements recently obtained at the Power Reactor and Nuclear Fuel Development Corporation (PNC) in an effort to improve the high temperature structural design methods for fast breeder reactor (FBR) components, are described in the area of the development of new structural materials, design analysis and assessment methods for specific components, advanced structural analysis methods, and improved structural strength evaluation methods. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 138
- Journal Issue
- 3
- Journal Page Range
- p. 269-282.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 24033575
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BELLOWS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION; CREEP; DEFORMATION; FATIGUE; FLOWSHEETS; LMFBR TYPE REACTORS; RATCHETING; REACTOR COMPONENTS; RESEARCH PROGRAMS; STRAIN RATE; TEMPERATURE RANGE 0400-1000 K; TUBES; WELDED JOINTS
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; DIAGRAMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; REACTORS; STAINLESS STEELS; STEELS; TEMPERATURE RANGE
Optional Information
- Notes
- Extended and updated paper from the 5th Japanese-German joint seminar, Munich (Germany), Oct 11-12, 1990.