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BOW. A computer code to predict lateral deflections of composite beams. A computer code to predict lateral deflections of composite beams

Abstract

Arrays of tubes are used in many engineered structures, such as in nuclear fuel bundles and in steam generators. The tubes can bend (bow) due to in-service temperatures and loads. Assessments of bowing of nuclear fuel elements can help demonstrate the integrity of fuel and of surrounding components, as a function of operating conditions such as channel power. The BOW code calculates the bending of composite beams such as fuel elements, due to gradients of temperature and due to hydraulic forces. The deflections and rotations are calculated in both lateral directions, for given conditions of temperatures. Wet and dry operation of the sheath can be simulated. Bow accounts for the following physical phenomena: circumferential and axial variations in the temperatures of the sheath and of the pellet; cracking of pellets; grip and slip between the pellets and the sheath; hydraulic drag; restraints from endplates, from neighbouring elements, and from the pressure-tube; gravity; concentric or eccentric welds between endcap and endplate; neutron flux gradients; and variations of material properties with temperature. The code is based on fundamental principles of mechanics. The governing equations are solved numerically using the finite element method. Several comparisons with closed-form equations show that the solutions of  More>>
Authors:
Publication Date:
Aug 15, 1987
Product Type:
Conference
Report Number:
AECL-9333; CONF-870812-
Reference Number:
SCA: 210400; 990200; PA: AIX-23:040105; SN: 92000732869
Resource Relation:
Conference: 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9), Lausanne (Switzerland), 17-21 Aug 1987
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FUEL ELEMENTS; BENDING; B CODES; CANDU TYPE REACTORS; FLOW STRESS; FUEL CANS; FUEL PELLETS; TEMPERATURE GRADIENTS; THERMAL STRESSES; 210400; 990200; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED; MATHEMATICS AND COMPUTERS
OSTI ID:
10144170
Research Organizations:
Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE92628219; TRN: CA9200216040105
Submitting Site:
INIS
Size:
16 p.
Announcement Date:
Jun 13, 1992

Citation Formats

Tayal, M. BOW. A computer code to predict lateral deflections of composite beams. A computer code to predict lateral deflections of composite beams. Canada: N. p., 1987. Web.
Tayal, M. BOW. A computer code to predict lateral deflections of composite beams. A computer code to predict lateral deflections of composite beams. Canada.
Tayal, M. 1987. "BOW. A computer code to predict lateral deflections of composite beams. A computer code to predict lateral deflections of composite beams." Canada.
@misc{etde_10144170,
title = {BOW. A computer code to predict lateral deflections of composite beams. A computer code to predict lateral deflections of composite beams}
author = {Tayal, M.}
abstractNote = {Arrays of tubes are used in many engineered structures, such as in nuclear fuel bundles and in steam generators. The tubes can bend (bow) due to in-service temperatures and loads. Assessments of bowing of nuclear fuel elements can help demonstrate the integrity of fuel and of surrounding components, as a function of operating conditions such as channel power. The BOW code calculates the bending of composite beams such as fuel elements, due to gradients of temperature and due to hydraulic forces. The deflections and rotations are calculated in both lateral directions, for given conditions of temperatures. Wet and dry operation of the sheath can be simulated. Bow accounts for the following physical phenomena: circumferential and axial variations in the temperatures of the sheath and of the pellet; cracking of pellets; grip and slip between the pellets and the sheath; hydraulic drag; restraints from endplates, from neighbouring elements, and from the pressure-tube; gravity; concentric or eccentric welds between endcap and endplate; neutron flux gradients; and variations of material properties with temperature. The code is based on fundamental principles of mechanics. The governing equations are solved numerically using the finite element method. Several comparisons with closed-form equations show that the solutions of BOW are accurate. BOW`s predictions for initial in-reactor bow are also consistent with two post-irradiation measurements.}
place = {Canada}
year = {1987}
month = {Aug}
}