High-temperature flaw assessment procedure: Interim report
Description
The current program represents a joint effort between the Electric Power Research Institute (EPRI) in the USA, the Central Research Institute of Electric Power Industry (CRIEPI) in Japan, and the Central Electricity Generating Board (CEGB) in the UK. The goal is to develop an interim high-temperature flaw assessment procedure for high-temperature reactor components. This is to be accomplished through exploratory experimental and analytical studies of high-temperature crack growth. The state-of-the-art assessment and the fracture mechanics database for both types 304 and 316 stainless steels, completed in 1988, serve as a foundation for the present work. Work in the three participating … continued below
Physical Description
107 pages
Creation Information
Ruggles, M.B.; Takahashi, Y. & Ainsworth, R. A. August 1, 1989.
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Oak Ridge National Laboratory
Publisher Info: Oak Ridge National Lab., TN (USA)Place of Publication: Tennessee
-
Electric Power Research Inst., Palo Alto, CA (USA)
Place of Publication: United States
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Description
The current program represents a joint effort between the Electric Power Research Institute (EPRI) in the USA, the Central Research Institute of Electric Power Industry (CRIEPI) in Japan, and the Central Electricity Generating Board (CEGB) in the UK. The goal is to develop an interim high-temperature flaw assessment procedure for high-temperature reactor components. This is to be accomplished through exploratory experimental and analytical studies of high-temperature crack growth. The state-of-the-art assessment and the fracture mechanics database for both types 304 and 316 stainless steels, completed in 1988, serve as a foundation for the present work. Work in the three participating organizations is progressing roughly on schedule. Results to-date are presented in this document. Fundamental tests results are discussed in Section 2. Section 3 focuses on results of exploratory subcritical crack growth tests. Progress in subcritical crack growth modeling is reported in Section 4. Exploratory failure tests are outlined in Section 5. 21 refs., 70 figs., 7 tabs.
Physical Description
107 pages
Notes
NTIS, PC A06/MF A01 - OSTI; 1.
Subjects
Keywords
- Alloys
- Asia
- Austenitic Steels
- B Codes
- Breeder Reactors
- Chromium Alloys
- Chromium-Nickel Steels
- Chromium-Nickel-Molybdenum Steels
- Computer Codes
- Coordinated Research Programs
- Corrosion Resistant Alloys
- Crack Propagation
- Cracks
- Cylinders
- Defects
- Epithermal Reactors
- Europe
- Fast Reactors
- Fatigue
- Fbr Type Reactors
- Finite Element Method
- Fracture Mechanics
- Heat Resis
- Heat Resistant Materials
- Heat Resisting Alloys
- High Alloy Steels
- Iron Alloys
- Iron Base Alloys
- Japan
- Liquid Metal Cooled Reactors
- Lmfbr Type Reactors
- Materials
- Mechanical Properties
- Mechanics
- Molybdenum Alloys
- Nickel Alloys
- North America
- Numerical Solution
- Pipes
- Reactor Components
- Reactor Materials
- Reactors
- Research Programs
- Stainless Steel-304
- Stainless Steel-316
- Stainless Steels
- Steel-Cr17Ni12Mo3
- Steel-Cr19Ni10
- Steels
- United Kingdom
- Usa
- Western Europe 210500* -- Power Reactors, Breeding
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- Other Information: Portions of this document are illegible in microfiche products
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- Other: DE89016457
- Report No.: ORNL/M-890
- Grant Number: AC05-84OR21400
- Digital Object Identifier: https://doi.org/10.2172/5769106
- Office of Scientific & Technical Information Report Number: 5769106
- Archival Resource Key: ark:/67531/metadc1095617
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Creation Date
- August 1, 1989
Added to The UNT Digital Library
- Feb. 18, 2018, 3:59 p.m.
Description Last Updated
- March 22, 2021, 3:28 p.m.
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Ruggles, M.B.; Takahashi, Y. & Ainsworth, R. A. High-temperature flaw assessment procedure: Interim report, report, August 1, 1989; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc1095617/: accessed July 18, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.