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Title: Development of variable width ribbon heating elements for liquid metal and gas-cooled fast breeder reactor fuel rod simulators

Abstract

Variable width ribbon heating elements have been fabricated which provide a chopped cosine, variable heat flux profile for fuel rod simulators used in test loops by the Breeder Reactor Program Thermal Hydraulic Out-of-Reactor Safety test facility and the Gas-Cooled Fast Breeder Reactor Core Flow Test Loop. Thermal, mechanical, and electrical design considerations result in the derivation of an analytical expression for the ribbon contours. From this, the ribbons are machined and wound on numerically controlled equipment. Postprocessing and inspection results in a wound, variable width ribbon with the precise dimensional, electrical, and mechanical properties needed for use in fuel pin simulators.

Authors:
; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
7065576
Report Number(s):
CONF-801091-8
TRN: 81-000110
DOE Contract Number:
W-7405-ENG-26
Resource Type:
Conference
Resource Relation:
Conference: International symposium on fuel rod simulators-development and application, Gatlinburg, TN, USA, 22 Oct 1980
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL PINS; SIMULATORS; GCFR TYPE REACTORS; TEST FACILITIES; HEATERS; PERFORMANCE TESTING; LMFBR TYPE REACTORS; ANALOG SYSTEMS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; FUNCTIONAL MODELS; GAS COOLED REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; 210500* - Power Reactors, Breeding

Citation Formats

McCulloch, R.W., Lovell, R.T., Post, D.W., and Snyder, S.D. Development of variable width ribbon heating elements for liquid metal and gas-cooled fast breeder reactor fuel rod simulators. United States: N. p., 1980. Web.
McCulloch, R.W., Lovell, R.T., Post, D.W., & Snyder, S.D. Development of variable width ribbon heating elements for liquid metal and gas-cooled fast breeder reactor fuel rod simulators. United States.
McCulloch, R.W., Lovell, R.T., Post, D.W., and Snyder, S.D. Tue . "Development of variable width ribbon heating elements for liquid metal and gas-cooled fast breeder reactor fuel rod simulators". United States. doi:. https://www.osti.gov/servlets/purl/7065576.
@article{osti_7065576,
title = {Development of variable width ribbon heating elements for liquid metal and gas-cooled fast breeder reactor fuel rod simulators},
author = {McCulloch, R.W. and Lovell, R.T. and Post, D.W. and Snyder, S.D.},
abstractNote = {Variable width ribbon heating elements have been fabricated which provide a chopped cosine, variable heat flux profile for fuel rod simulators used in test loops by the Breeder Reactor Program Thermal Hydraulic Out-of-Reactor Safety test facility and the Gas-Cooled Fast Breeder Reactor Core Flow Test Loop. Thermal, mechanical, and electrical design considerations result in the derivation of an analytical expression for the ribbon contours. From this, the ribbons are machined and wound on numerically controlled equipment. Postprocessing and inspection results in a wound, variable width ribbon with the precise dimensional, electrical, and mechanical properties needed for use in fuel pin simulators.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1980},
month = {Tue Jan 01 00:00:00 EST 1980}
}

Conference:
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  • Variable-width ribbon heating elements that provide a chopped-cosine variable heat flux profile have been fabricated for fuel pin simulators used in test loops by the Breeder Reactor Program Thermal-Hydraulic Out-of-Reactor Safety test facility and the Gas-Cooled Fast Breeder Reactor-Core Flow Test Loop. Thermal, mechanical, and electrical design considerations are used to derive an analytical expression that precisely describes ribbon contour in terms of the major fabrication parameters. These parameters are used to generate numerical control tapes that control ribbon cutting and winding machines. Infrared scanning techniques are developed to determine the optimum transient thermal profile of the coils and relatemore » this profile to that generated by the coils in completed fuel pin simulators.« less
  • From symposium on fuel and elements for fast reactors; Brussels, Belgium (2 Jul 1973). Results of irradiation testing of fuel rods for the Gas-cooled Fast Breeder Reactor (GC FR) are presented. It was found that under GCFR conditions volatile fission products were not observed beyond the fuel end of the blanket region in the GB-9 rod, which operated with no simulation of a cladding leak. This means that for normal operation up to the maximum burnup maintained in the GB-9 rod, i.e., 54,000 MWd/t, the charcoal trap was not required to limit transport of volatile fission products out of themore » fuel rod. No significant dimensional change was observed for the fuel rod irradiated to a burnup of 54,000 MWd/t. Attack of the cladding by fuel or fission products is in agreement with that observed in sealed rods tested under the LMFBR program. The observed gaseous fission-product releases and transport rates under steady-state conditions have verified the models being employed for systems analysis. The behavior of the gaseous fission products during transients of temperature, power, and pressure was in agreement with analytical predictions. Solidstate migration and gas-phase interdiffusion limit the rate of the release of gaseous fission products during normal operation. However, when a simulated leak is introduced, convective transport becomes dominant. The delay of gaseous fission products by the rod charcoal traps was as predicted over a temperature range simulatlng both normal and off-desfgn GC FR operation. (JRD)« less
  • Early fuel removal from the active core of a liquid-metal-cooled fast breeder reactor undergoing a core-disruptive accident may reduce the potential for large energetics resulting from recriticalities. This paper presents a review of analyses with the SIMMER-II computer program of the effectiveness of possible fuel escape paths. Where possible, how SIMMER-II compares with or is validated against experiments that simulated the escape paths also is discussed.