Actions for Inelastic analysis of two pipelines in the Fast Flux Test Facility [electronic resource].
Inelastic analysis of two pipelines in the Fast Flux Test Facility [electronic resource].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
- Physical Description
- Pages: 18 : digital, PDF file
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Several complex pipelines of the Fast Flux Test Facility (FFTF) were evaluated using detailed inelastic analysis because they did not satisfactorily comply with the ASME elastic analysis rules. The purpose of the inelastic analysis is to demonstrate that the piping systems, which operate at elevated temperatures, comly with ASME Code requirements under the loading conditions specified in the Design Specification of each pipeline, using inelastic analysis rules. Two pipelines are discussed, the 8-inch Secondary Hot Leg in the Heat Transport System and the 3-inch/4-inch Primary Hot Leg (Ex-module) in the Closed Loop System. The former is made from type 304SS, operating at 965/sup 0/F (518.3/sup 0/C) and designed for a 20 year life; the latter is made from type 316SS, operating at 1200/sup 0/F (648.9/sup 0/C) and designed for a 10 year life. The MARC general finite element computer program was utilized in the analyses. The pipelines were idealized using the combinations of thin-walled circular closed section beam elements and constant bending 3-node elbow elements. Discussions on the load histograms used, the inelastic strain accumulated, and the effects of creep and fatigue on the lines are given.
- Report Numbers
- E 1.99:hedl-sa-1641
E 1.99: conf-790615-24
conf-790615-24
hedl-sa-1641 - Subject(s)
- Other Subject(s)
- Fftf Reactor
- Reactor Cooling Systems
- Finite Element Method
- Pipelines
- Stainless Steel-304
- Stress Analysis
- Alloys
- Chromium Alloys
- Chromium Steels
- Chromium-Nickel Steels
- Cooling Systems
- Corrosion Resistant Alloys
- Epithermal Reactors
- Fast Reactors
- Heat Resistant Materials
- Heat Resisting Alloys
- Iron Alloys
- Iron Base Alloys
- Liquid Metal Cooled Reactors
- Materials
- Nickel Alloys
- Numerical Solution
- Reactor Components
- Reactors
- Research And Test Reactors
- Research Reactors
- Sodium Cooled Reactors
- Stainless Steels
- Steels
- Test Reactors
- Note
- Published through SciTech Connect.
01/01/1979.
"hedl-sa-1641"
" conf-790615-24"
3. US national congress on pressure vessels and piping, San Francisco, CA, USA, 25 Jun 1979.
Huang, S. N.
Hanford Engineering Development Lab., Richland, WA (USA) - Funding Information
- EY-76-C-14-2170
View MARC record | catkey: 14803815