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Supplement A to design of PT-IP-263-A-FP, evaluation of chemically nickel plated fuel elements

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 pilo… more
Date: August 22, 1961
Creator: Clinton, M. A. & Hodgson, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical bases for C-pile overbore test

Description: The production gains and economic evaluation of overboring has been extensively treated. In this document, the justification for a trial attempt at overboring C-Reactor was given. The overboring test, covered by two production tests (one or overboring and one for fuel irradiation), requires the integration of efforts of Equipment Development, Process and Reactor Development, Process Technology, Manufacturing, and the Fuels Preparation Department. In view of this, it appears prudent to collect i… more
Date: November 3, 1960
Creator: Curtiss, D. H.; Clinton, M. A. & Nechodom, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement A to PT-IP-263-A-FP evaluation of chemically nickel plated fuel elements

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 fue… more
Date: July 10, 1961
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Supplement A to PT-IP-183-A-98-FP: Evaluation of projection fuel elements for use in K process tubes

Description: The objective of this supplement is to authorize charging of ten tubes of ``bumper`` fuel elements and controls into each K Reactor. The test is designed to reevaluate the reduction in hot-spot incidence associated with fuel alignment within K Reactor ribbed process tubes for both natural and enriched uranium I&E fuel elements of the KIV geometry.
Date: April 10, 1961
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT-IP-263-A-FP: Evaluation of chemically nickel plated fuel elements

Description: 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 eig… more
Date: April 20, 1960
Creator: Hall, R. E. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test IP-490-A-FP: Evaluation of diffusion bonded fuel elements

Description: The objectives of this test are to determine the gross dimensional stability of hot pressed fuel and to evaluate bond quality differences between Al-Si bonds and solid state diffusion bonds. Irradiation testing will be conducted at C Reactor and will be carried out in two parts: Part 1, Sylcor and Hanford hot press diffusion bonding processes will be compared to the Hanford Al-Si bonding process. Eighteen (18) measured monitor columns of CVNS fuel elements will be irradiated to an 800 MWD/T goa… more
Date: May 2, 1962
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PITA IP-27-I, Part 1 increased coolant flow, H reactor

Description: The PITA`s (process improvement transition authorizations) present the specific requirements necessary to accomplish the outage work and to control the use of this increased flow capability. The procedures and methods to accomplish the programmed modifications are contained in the approve design changes or in supplemental procedures.
Date: December 20, 1963
Creator: Clinton, M. A. & Spicka, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: Since it is now possible to obtain a heat-treated U core that is randomly oriented and has a finer average grain size, it is necessary to irradiate measured, transformed fuel cores over the full range of grain sizes, in order to compare relative dimensional stabilities. An improved ultrasonic tester, Fuel Core Tester-UT-2, is used to test all fuel cores.
Date: April 27, 1961
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test-IP-409-A-FP pilot test of self-supported fuel elements in K size smooth-bore zirconium process tubes

Description: This test authorizes installation of up to ten non-overbore size zirconium smooth-bore process tubes into KW Reactor and continued charging of these tubes with KVNS fuel elements until authorized by other means (Process Standards or PITA) or until this test is terminated. While the test authorizes up to 10 tubes, only two process tubes are immediately available and are all that will be planned for in the initial installation and charging. Goal exposure will be set at 800 MWD/T.
Date: June 19, 1961
Creator: Clinton, M. A. & Curtiss, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim report one to Production Test-IP-549-A, half-plant low alum feed water treatment at F Reactor

Description: A half-plant low alum water treatment test began at F Reactor on January 16, 1963 at startup from the scheduled January 3 tube replacement outage. The test, which was prompted by results obtained from a statistical analysis of fuel ledge corrosion attack, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production… more
Date: February 11, 1963
Creator: Clinton, M. A. & Geier, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test IP-432-A-FP, Evaluation of the corrosion characteristics of elliptical bumper rails

Description: Twenty columns of OIIIN-B fuel elements, ten with bumper rails of the present design and ten with elliptical bumper rails, will be charged into D Reactor in pairs, i.e., a column of fuel elements with one rail design will be charged adjacent to a column containing the other bumper rail design. Performance of the elliptical bumper rail will be based on relative visual appearance and measured weight loss. The twenty columns of weight and measured fuel elements required for this test may also be u… more
Date: October 2, 1961
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT-IP-344-A-FP, Evaluation of Al-Si bond characteristics

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can-bond separation following irradiation. Such evidence h… more
Date: November 10, 1961
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of supplement A to production test IP-183-A-98-FP evaluation of projection fuel elements in K process tubes

Description: Fuel element misalignment is an apparent cause of ``hot-spot`` ruptures. Several methods of eliminating hot spots have been tried, however, none appear to have completely solved the hot-spot problem. Attachment of projections to the side of the fuel elements appears to offer a means of minimizing misalignment since they act as bumpers against the side of the process tubes. Preliminary data from tests now in progress or recently completed indicate excessive corrosion rates are not to be expected… more
Date: July 27, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-468-A-FP, Program for evaluation of alpha extruded fuel cores

Description: Currently, all normal production HAPO fuel cores are rolled into rods at Fernald, consequently, HAPO is dependent upon one vendor for a critical raw material. This arrangement does not appear to be consistent with good business practice, and it is desirable to have an alternate fuel source tested and available. Mallinckrodt`s Weldon Spring plant contains an extrusion press for the gamma bar extrusion and a logical sequence of operations should permit further extrusion in the alpha phase to the … more
Date: January 31, 1962
Creator: Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-555-A sodium silicate as a corrosion inhibitor

Description: The objective of this test is to operate one of the 1706-KE single pass tubes using sodium silicate rather than sodium dichromate as the corrosion inhibitor and to monitor the radioisotope concentration in the effluent. Single pass tube tests carried out under Production Test IP-484-A have demonstrated that when sodium silicate is added to process water the concentrations of significant radioisotopes in the effluent are reduced by a factor of two. At the concentrations investigated., the use of… more
Date: December 17, 1962
Creator: Geier, R. G. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-289-I H Reactor process pump trip-out-test

Description: The objectives of this test are to obtain a current knowledge of the H Reactor flow system characteristics under various transient conditions which have a reasonable probability of occurrence. The test data will be used to revaluate: (1) the H Reactor bulk effluent temperature limits, (2) the margin between the Ball 3X riser pressure trip settings, and (3) the quantitative adequacy of emergency flow available from the combined high tanks export system. This test will consist of two parts: (a) M… more
Date: October 13, 1959
Creator: Clinton, M. A.; Long, J. T. & Jones, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-423-A-FP evaluation of uranium fuel cores having virus heat treatments

Description: Fuel element warp occurring during the irradiation period is considered to be one of the major fuel element dimensional stability problems. Warp has been shown to correlate with accelerated corrosion attack. and also can contribute to stuck fuel charges, particularly in bumpered or self-supported charges where the annular clearances are reduced due to the presence of the projection rails. Thus, any process which offers a potential for reducing the average warp should be evaluated. Preliminary t… more
Date: January 5, 1962
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-468-A-FP, program for evaluation of alpha extruded fuel cores

Description: The alpha phase extrusion of dingot bars to rods for core blank heat treatment at MCW offers a three-fold incentive, including: (1) establishment of an independent alternate source of uranium cores, (2) a slight cost improvement of MCW extrusion over FMPC rolling of dingot and (3) potential improvement in core quality and performance. The purpose of this test is two-fold: (1) to evaluate gross dimensional stability and (2) to evaluate the gross irradiation performance of alpha phase extruded di… more
Date: January 28, 1962
Creator: Clinton, M. A. & Hodgson, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-490-A-FP evaluation of diffusion bonded fuel elements

Description: I&E uranium cores are to be jacketed by Sylcor and Hanford utilizing the ``Solid State Diffusion-Hot Pressure Bonding`` process. Hanford will also jacket cores by the ``Solid State Diffusion`` process, by ``Gas Pressure Bonding`` and ``Hot Die Sizing``. In this process, a layer of nickel is placed between the aluminum and uranium to prevent diffusion of the aluminum into the uranium and furnish a layer of metal capable of limiting diffusion with both the aluminum and uranium. The completed fuel… more
Date: March 26, 1962
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mix… more
Date: February 15, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-409-A-FP, pilot test of self-supported fuel elements in K size smoothbore zirconium process tubes

Description: In the Plant Improvement Program, it is proposed to retube the K-Reactors with standard size Zircaloy-2 smooth-bore process tubes and to charge self supported fuel elements starting March 15, 1964. The first step in support of this transition program is to confirm compatibility of the fuel-tube geometry and secondly to obtain fuel-tube performance information prior to full scale commitment of the K-Reactors to this design. In view of the testing of self-supported fuel which has been accomplishe… more
Date: July 26, 1961
Creator: Clinton, M. A. & Hodgson, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of Production Test IP-381-A-FP, Irradiation of oversize fuel elements in the C Reactor overbored process channel facilities

Description: Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and five old reactors, under the updated Plant Improvement Program. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work, an increase in plutonium production of 15--18%, derived from increased conversion ratio and a reduction in plant unit cost. The proposal to overbore the graphite channels app… more
Date: January 6, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status report: Protection fuel testing program, July 1960

Description: The program`s objective is to develop the technical foundation for use of projection fuel elements through an accelerated testing program. Two types of projection fuel elements are being considered (1) Self-supported fuel elements for use in ribless aluminum or zirconium process tubes; and (2) Bumper fuel elements for use in ribbed process tubes. A further objective of the program is to determine the most desirable method of fabrication and type of support for projection fuel elements. The prog… more
Date: July 15, 1960
Creator: Clinton, M. A. & Peacock, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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