Supplement A to PT-IP-263-A-FP Evaluation of Chemically Nickel Plated Fuel Elements PDF Download
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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 : 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-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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ISBN:
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.
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Category :
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.
Author: M. A. Clinton
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Category :
Languages : en
Pages : 20
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Author: R. E. Hall
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Category :
Languages : en
Pages : 8
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Author: W. H. Hodgson
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Category :
Languages : en
Pages : 18
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Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 188
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Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.
Author: Naval Sea Systems Command
Publisher:
ISBN: 9780359793839
Category :
Languages : en
Pages : 454
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Chapter 1 ELECTRICAL REVIEW 1.1 Fundamentals Of Electricity 1.2 Alternating Current Theory 1.3 Three-Phase Systems And Transformers 1.4 Generators 1.5 Motors 1.6 Motor Controllers 1.7 Electrical Safety 1.8 Storage Batteries 1.9 Electrical Measuring Instruments Chapter 2 ELECTRONICS REVIEW 2.1 Solid State Devices 2.2 Magnetic Amplifiers 2.3 Thermocouples 2.4 Resistance Thermometry 2.5 Nuclear Radiation Detectors 2.6 Nuclear Instrumentation Circuits 2.7 Differential Transformers 2.8 D-C Power Supplies 2.9 Digital Integrated Circuit Devices 2.10 Microprocessor-Based Computer Systems Chapter 3 REACTOR THEORY REVIEW 3.1 Basics 3.2 Stability Of The Nucleus 3.3 Reactions 3.4 Fission 3.5 Nuclear Reaction Cross Sections 3.6 Neutron Slowing Down 3.7 Thermal Equilibrium 3.8 Neutron Density, Flux, Reaction Rates, And Power 3.9 Slowing Down, Diffusion, And Migration Lengths 3.10 Neutron Life Cycle And The Six-Factor Formula 3.11 Buckling, Leakage, And Flux Shapes 3.12 Multiplication Factor 3.13 Temperature Coefficient...
Author:
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ISBN:
Category : Polycyclic aromatic hydrocarbons
Languages : en
Pages : 500
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