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Title: Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318)

Abstract

This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two longitudinal planes at the male end. The distortion planes are at right angles which gives the transverse section a square a appearance. A comparison of the grain size from three positions along the warped element with a section cut from the unwarped element revealed a greater number of large grains in the zones of highest distortion. The maximum size grains, were in the order of 2.5 mm -- 3.8 mm vs normal .2 mm. Also prevalent in all sections examined vas a columnar type grain structure around the outside periphery. It is evident that the pre-irradiation heat treatment failed to refine the grain size sufficiently to prevent nonuniform growth of this element during irradiation. A corrosion pit wasmore » noticed in the canwall of the second element that had penetrated of the canwall.« less

Authors:
Publication Date:
Research Org.:
General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10175842
Report Number(s):
HW-62732
ON: DE94017251
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: DN: Declassified; PBD: 12 Nov 1959
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; HANFORD PRODUCTION REACTORS; FUEL ELEMENTS; POST-IRRADIATION EXAMINATION; DEFORMATION; IRRADIATION; GRAIN SIZE; HEAT TREATMENTS; CORROSION; 220600; 220300; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS

Citation Formats

Teats, R. Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318). United States: N. p., 1959. Web. doi:10.2172/10175842.
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Teats, R. Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318). United States. doi:10.2172/10175842.
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Teats, R. Thu . "Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318)". United States. doi:10.2172/10175842. https://www.osti.gov/servlets/purl/10175842.
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@article{osti_10175842,
title = {Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318)},
author = {Teats, R.},
abstractNote = {This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two longitudinal planes at the male end. The distortion planes are at right angles which gives the transverse section a square a appearance. A comparison of the grain size from three positions along the warped element with a section cut from the unwarped element revealed a greater number of large grains in the zones of highest distortion. The maximum size grains, were in the order of 2.5 mm -- 3.8 mm vs normal .2 mm. Also prevalent in all sections examined vas a columnar type grain structure around the outside periphery. It is evident that the pre-irradiation heat treatment failed to refine the grain size sufficiently to prevent nonuniform growth of this element during irradiation. A corrosion pit was noticed in the canwall of the second element that had penetrated of the canwall.},
doi = {10.2172/10175842},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Nov 12 00:00:00 EST 1959},
month = {Thu Nov 12 00:00:00 EST 1959}
}
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Technical Report:
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DOI:  10.2172/10175842
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  • Eight Zircaloy-2 jacketed, natural uranium seven-rod cluster elements were irradiated in a KER loop to determine flow channel temperature characteristics. One of the elements, which had 200 MWD/T exposure, was sent to the Radiometallurgy Laboratory for examination in April 1959. An outside rod of the cluster was sectioned and examined metallographically. No cracks or flaws were observed in the uranium cladding or bonding.

  • During the examination of the first two elements received, some incipient corrosion pitting was found in the can wall under the support tabs. Two other elements were examined; no evidence of any corrosion was found that might seriously affect canwall integrity.

  • Under the conditions of PT-IP-247-A, four columns of self-supported and four columns of rib-supported I&E 1.47% enriched fuel elements were irradiated to determine their relative performance under severe operating conditions. Four of the self-supported and two of the rib-supported control elements were received for nation. The two rib-supported control pieces, which were classified as ``near failures`` had received average exposures of 353 and 359 MWD/T at average specific power levels of 91 and 108 KW/ft before they were discharged because of other ruptured pieces in the tubes. The nominal specified canned fuel dimensions of the rib supported elements was 1.445more » in. OD, .310 in bore, and 7.640 in. long. The first two self-supported elements were selected for examination on the basis of high weight losses sustained during irradiation, and the second two were selected to determine the effect of specific power levels on the AlSi bonding. The average specific power levels of the four self-supported elements varied from 79 to 110 KW/ft and the exposure varied from 845 MWD/T to 949 MWD/T. The nominal canned dimensions of the self-supported elements, which were made oversize to attain high annular coolant temperatures with respect to the interior coolant channel, were 1.460 in. OD, .375 in. bore, and 7.640 in. long. The eight bridge rail supports were spot welded on and gave an effective rib outside diameter of 1.600 in. All of the components were X-8001 aluminum alloy.« less

  • Two chemically nickel-plated, internally and externally cooled, Hanford production fuel elements, which were irradiated to approximately 800 MWD/T as part of PT-IP-263-A, were transferred to the Radiometallurgy Laboratory in December 1960. The elements were selected for detailed examination because one had incurred a hot spot during irradiation and the other contained some unusual cracks in the nickel plate. Prior to irradiation, both fuel elements had been baked at 300 C to heat-treat the nickel plate. Also, the nickel plate of several unirradiated elements was damaged by scraping, marring, scratching and punching. The elements were exposed for six weeks to 105more » C basin water, which was approximately the length of time the irradiated elements were in 105 C basin prior to transfer. Two unirradiated elements were submitted for comparison with irradiated pieces. The examination was requested by Process Engineering, Fuels Preparation Department; and Process and Reactor Development, Irradiation Processing Department, to determine the effects of irradiation on elements with improved nickel plating and to aid in evaluating the nickel-plated fuel element program.« less