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Title: A simplified model of core thermal dilation

Abstract

A simple analytical model is developed of core radial expansion for a fast reactor using a limited-free-bow core restraint design. The model is restricted to those bowing regimes where the plane of above core load pads (ACLP) is compacted to the point where the outermost driver assemblies are restrained at the ACLP from further compaction by a continuous network of contacting load pads, and where the top load pads (TLP) of the outer driver assemblies are restrained from further radial expansion by continuous load paths to the TLP restraint ring. Essentially elementary beam theory is used to calculate the elastic bow of a driver assembly at the core periphery subject to temperature dependent boundary conditions at the nozzle support, ACLP and TLP and subject to thermal and inelastic bowing deformations. The following design parameters are considered: grid plate temperature, core temperature rise, restraint ring temperature, grid plate and restraint ring thermal expansion coefficients, duct material properties (thermal expansion, swelling and creep), nozzle support condition, core radius, core axial location, core height, driver assembly radial thermal gradient, ACLP location and compressibility, and gaps at the ACLP and TLP elevations.

Authors:
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
OSTI Identifier:
5746048
Report Number(s):
CONF-8709192-2
ON: DE88002972
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: Annual NEACRP meeting, Helsinki, Finland, 14 Sep 1987; Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; REACTIVITY; REACTOR CORES; DEFORMATION; THERMAL EXPANSION; REACTOR MATERIALS; CREEP; EXPERIMENTAL DATA; MATHEMATICAL MODELS; N CODES; SWELLING; BREEDER REACTORS; COMPUTER CODES; DATA; EPITHERMAL REACTORS; EXPANSION; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICAL PROPERTIES; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; 210500* - Power Reactors, Breeding

Citation Formats

Moran, T J. A simplified model of core thermal dilation. United States: N. p., 1987. Web.
Moran, T J. A simplified model of core thermal dilation. United States.
Moran, T J. Thu . "A simplified model of core thermal dilation". United States. https://www.osti.gov/servlets/purl/5746048.
@article{osti_5746048,
title = {A simplified model of core thermal dilation},
author = {Moran, T J},
abstractNote = {A simple analytical model is developed of core radial expansion for a fast reactor using a limited-free-bow core restraint design. The model is restricted to those bowing regimes where the plane of above core load pads (ACLP) is compacted to the point where the outermost driver assemblies are restrained at the ACLP from further compaction by a continuous network of contacting load pads, and where the top load pads (TLP) of the outer driver assemblies are restrained from further radial expansion by continuous load paths to the TLP restraint ring. Essentially elementary beam theory is used to calculate the elastic bow of a driver assembly at the core periphery subject to temperature dependent boundary conditions at the nozzle support, ACLP and TLP and subject to thermal and inelastic bowing deformations. The following design parameters are considered: grid plate temperature, core temperature rise, restraint ring temperature, grid plate and restraint ring thermal expansion coefficients, duct material properties (thermal expansion, swelling and creep), nozzle support condition, core radius, core axial location, core height, driver assembly radial thermal gradient, ACLP location and compressibility, and gaps at the ACLP and TLP elevations.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {1}
}

Conference:
Other availability
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