Published November 15, 1978
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Analytical study of the dilation of fast reactor fuel assembly ducts
Description
An analytic method is presented for determining the dilation of fast reactor fuel assembly ducts. For temperatures where creep is linearly dependent on stress, the method is rigorous in satisfying equilibrium, compatibility and stress-strain equations. Solutions are presented for two cases: (1) a duct with constant pressure differential, (2) a duct with varying pressure differential. Results are in close agreement with finite element results of the MARC-CDC program. The method is used to predict the dilation of the Fast Test Reactor (FTR) ducts under different operating conditions. Presented are the stress, strain and dilation predictions along the duct wall, and the duct dilation variations with its geometric and loading parameters
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11518211.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- HEDL-SA--1677
Conference
- Title
- International conference on structural mechanics in reactor technology.
- Dates
- 13 - 17 Aug 1979.
- Place
- Berlin, F.R. Germany.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11518211
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; DEFORMATION; FFTF REACTOR; FUEL ASSEMBLIES; PRESSURE GRADIENTS; THERMAL STRESSES
- Descriptors DEC
- EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STRESSES; TEST REACTORS
Optional Information
- Secondary number(s)
- CONF-790802--75.