Post-irradiation Examination of Chemically Nickel-plated Fuel Elements from PT-IP-263-A (RM-414). PDF Download
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Languages : en
Pages : 14
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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 105 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.
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Category :
Languages : en
Pages : 14
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Book Description
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 105 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.
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Category :
Languages : en
Pages : 11
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Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-8001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify the performance of nickel-plate with a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis. The objectives of this test are to demonstrate with a larger scale test that nickel-plate performs satisfactorily and that reducing the nominal plate thickness from .6 mil to .2 mil will not affect the performance of the nickel-plate fuel element. This test authorizes the irradiation of up to 100 columns of OIIN, chemically nickel-plated, C-64 alloy jacketed fuel elements to 200% of normal goal exposure to extend the evaluation of nickel-plated fuel elements on a pilot scale at DR Reactor. Seventy columns will be plated to a nominal thickness of .6 mil and thirty columns to a nominal .2 mil thickness. Twenty measured columns, ten representing each plate thickness, will be charged to monitor the irradiation performance. Effluent samples will be obtained during the course of the test from a pair of tubes, each tube containing a measured monitor charge representing each plate thickness.
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Category :
Languages : en
Pages : 9
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A .0005 inch thick chemically nickel plated, C-64 aluminum clad, natural uranium, internally and externally cooled, Hanford production fuel element, which had incurred a ''side hot spot'' during irradiation, was shipped to the Radiometallurgy Laboratory in June 1959 for post irradiation examination. The slug vas irradiated to approximately 400 MWD/T in C Reactor as part of PT-IP-207-A. The examination was requested by personnel from Process Engineering, Fuels Preparation Department and Process and Reactor Development, Irradiation Preparation Department to determine the irradiation behavior cf nickel plated fuel elements and to aid in evaluating the nickel plated fuel element program. The presence of the nickel plate probably averted a ''side hot spot'' failure. Al-Si spheroidization and Ni-Al diffusion indicated that the maximum surface temperature vas 325--350°C for at least one hundred hours, however no sloughing of the nickel vas seen in the ''hot spot.'' Sloughing of the nickel plate, associated with poor nickel bonding, vas observed near the cap end of the slug. The condition my have been aggravated by the formation of hydrogen gas originating from the diffusion of atomic hydrogen through and/or from the nickel plate into the voids between the nickel and aluminum in poorly banded areas. Observations prompted the establishing of tests of other nickel plated slugs from PT-IP-207-A to determine whether or not hydrogen gas vas being trapped under the plate. These tests are currently in progress. The aluminum canwall was attacked intergranularly in a few localized areas near the cap end of the slug. The attack was observed only where a crack in the nickel plate was coincided with an unbonded area of the nickel and aluminum. There was no undercutting of the plate by corrosion to cause sloughing of the nickel.
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Category :
Languages : en
Pages : 11
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Book Description
Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-80001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved, as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify that the nickel-plate integrity problem has been solved by irradiating a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis.
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Category :
Languages : en
Pages : 10
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The objective of this test is to determine, through in-reactor testing, the resistance to corrosion of nickel plated fuel elements, plated by a chemical deposition technique. This program may eventually be composed of the following portions, the first of which is authorized by this test: (1) Irradiate ten columns of 0.5 mil chemically nickel-plated C-64 OIIN fuel elements having various heat treatments, each alternated with x-8001 control pieces. Two columns will be exposed to 400 MWD/T and eight to 800 NWD/T. (2) Should results from the above test be encouraging, separate authorization for the following tests may be requested: (a) Irradiate four columns of nickel-plated fuel and four of X-8001 clad fuel, both groups having purposely cocked pieces, until two ruptures are sustained in each group or until a factor of improvements of 400 is demonstrated at the 95% confidence level, unless the nickel-plated elements fail first. (b) Irradiate five columns of chemically nickel-plated C-64 clad OIIN fuel elements, alternating 0.2 mil and 0.5 mil plate, heat treated at 300°C for six hours. Two columns will be discharged at 400 MWD/T and three columns at 800 MWD/T exposure. (c) Irradiate approximately thirty columns of nickel-plated, C-64 alloy clad fuel elements to 200 per cent of normal goal exposure to extend the evaluation of nickel-plated fuel elements on a pilot scale.
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149
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Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.
Author: W. J. Gruber
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
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Author: K. D. Cotnam
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Category :
Languages : en
Pages : 0
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ISBN:
Category :
Languages : en
Pages : 5
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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.
Author: H. B. Meieran
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 86
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