Published November 15, 1978 | Version v1
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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.

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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.