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Effects of spacers on blockage of coolant channels in clad melting accidents

Abstract

The elements and configuration of these assemblies are representative of the current design for a GCFR. The fuel elements are stainless-steel clad, mixed-oxide spaced by a grid structure on 250 mm centers with a pitch of 9.5 mm, diameter, 7.2 mm, and cladding thickness, 0.5 m. Three series of experiments have been conducted to study the flow and disposition of molten cladding metal into a lower powered blanket region of the reactor following a loss of flow situation. The first two series used a simulant fuel-element bundle to simplify the experimental procedure and make visual observation possible. The 'fuel' was simulated by mullite rods 6.4 mm in diameter and 610 mm long. These were clad with a 50 Pb/50 Sn alloy tubing which was drawn onto the 'fuel'. The first series used cast spacers with webs of about 0.5-0.55 mm thickness placed 175 and 425 mm from the top end of the assembly. The second series used grid spacers fabricated of 0.25 mm alloy strips. This provided a more accurate representation of the hydraulic diameter. The bundle was encased in a hexagonal glass tube. The bundle was at 22/sup 0/C and the molten alloy was poured at a temperature of  More>>
Authors:
Eggen, D. T.; Scale, T.; Hsieh, S. [1] 
  1. Northwestern Univ., Evanston, IL (United States). The Technological Inst.
Publication Date:
Jul 01, 1977
Product Type:
Conference
Report Number:
INIS-mf-4592; CONF-770807-(Pt.E)
Reference Number:
AIX-10-426537; ERA-04-054908; EDB-79-117467
Resource Relation:
Conference: 4. international conference on structural mechanics in reactor technology, San Francisco, CA, USA, 15-19 Aug 1977; Related Information: Part of Transactions of the 4th international conference on structural mechanics in reactor technology, Vol. E. Structural Dynamics in Fast Reactor Accident Analysis
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; GCFR TYPE REACTORS; FUEL CANS; REACTOR CHANNELS; LOSS OF COOLANT; FUEL ASSEMBLIES; OXIDES; SPACERS; STAINLESS STEELS; ACCIDENTS; ALLOYS; BREEDER REACTORS; CHALCOGENIDES; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; STEELS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding
OSTI ID:
6025400
Research Organizations:
Commission of the European Communities, Brussels (Belgium)
Country of Origin:
CEC
Language:
English
Submitting Site:
INIS
Size:
9 p.
Announcement Date:

Citation Formats

Eggen, D. T., Scale, T., and Hsieh, S. Effects of spacers on blockage of coolant channels in clad melting accidents. CEC: N. p., 1977. Web.
Eggen, D. T., Scale, T., & Hsieh, S. Effects of spacers on blockage of coolant channels in clad melting accidents. CEC.
Eggen, D. T., Scale, T., and Hsieh, S. 1977. "Effects of spacers on blockage of coolant channels in clad melting accidents." CEC.
@misc{etde_6025400,
title = {Effects of spacers on blockage of coolant channels in clad melting accidents}
author = {Eggen, D. T., Scale, T., and Hsieh, S.}
abstractNote = {The elements and configuration of these assemblies are representative of the current design for a GCFR. The fuel elements are stainless-steel clad, mixed-oxide spaced by a grid structure on 250 mm centers with a pitch of 9.5 mm, diameter, 7.2 mm, and cladding thickness, 0.5 m. Three series of experiments have been conducted to study the flow and disposition of molten cladding metal into a lower powered blanket region of the reactor following a loss of flow situation. The first two series used a simulant fuel-element bundle to simplify the experimental procedure and make visual observation possible. The 'fuel' was simulated by mullite rods 6.4 mm in diameter and 610 mm long. These were clad with a 50 Pb/50 Sn alloy tubing which was drawn onto the 'fuel'. The first series used cast spacers with webs of about 0.5-0.55 mm thickness placed 175 and 425 mm from the top end of the assembly. The second series used grid spacers fabricated of 0.25 mm alloy strips. This provided a more accurate representation of the hydraulic diameter. The bundle was encased in a hexagonal glass tube. The bundle was at 22/sup 0/C and the molten alloy was poured at a temperature of 260/sup 0/C (35/sup 0/C superheat). Motion pictures recorded the experiments and the bundle was sectioned for observation. The third set of experiments was done with a stainless steel bundle of 37 elements fabricated of mullite rods, 7.14 mm diameter. The stainless steel cladding had an O.D. of 8.41 mm. The element pitch was 11.1 mm. The grid spacers were prototypic. The experiment was conducted in an inert-gas tube furnace. The 'core fuel' cladding was melted in an induction furnace and the molten liquid flowed through the center seven element channels. X-ray pictures were taken after the tests and the bundle was sectioned for further study.}
place = {CEC}
year = {1977}
month = {Jul}
}