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Status of special reactor process tube loadings, December 1, 1965

Description: This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. Data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document RL-REA-837.
Date: December 8, 1965
Creator: Bown, R.W.
Partner: UNT Libraries Government Documents Department

Semiannual research and development report, Douglas United Nuclear, Inc.

Description: Initially the O2 Research and Development Program for Douglas United Nuclear, Inc., for FY 1966 was contained in six 189-forms R-1 through R-4 and M-1 and M-2. Although the authors are currently in a period of transition to the Five Year Research and Development Program, this document reports on the programs as originally set forth. The subprograms designated by R pertain to reactor research and development, and those designated by M pertain to metallurgy or fuels research and development. The report covers the progress in each of the subprograms on an individual basis for the period July 1, 1965 through october 31, 1965. Although the reports are brief, they are complete. A few of the items are listed in the reports on the subprograms that have been performed on product cost funds but were made possible by earlier research and development effort. The following programs are covered: (1) radioisotope reduction reactor effluent; (2) nuclear and radiation safety; (3) production of clean U-233; (4) production development studies; (5) alternate cladding process; and (6) fuel development.
Date: November 30, 1965
Creator: Ambrose, T.W.
Partner: UNT Libraries Government Documents Department

Status of special reactor process tube loadings, February 1, 1966

Description: This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. Data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document RL-REA-837.
Date: February 10, 1966
Creator: Bown, R.W.
Partner: UNT Libraries Government Documents Department

Iron-masonite shield status interim report No. 6

Description: This is number six in a planned series of reports intended to show the status and rates of deterioration of the iron-masonite biological shields of B, Dg DR, F, and H reactors. Since DR, F, and H reactors are in the deactivated state this is the final such report for them. Following the deactivation of D Reactor at the end of June, 1967, B Reactor will be the only one (out of the five with which the shield deterioration study began) to continue operating. Data for this report pertain to the top and left (far) side of the reactors and covers the period from January, 1963, through December, 1966.
Date: June 30, 1967
Creator: Clark, D.E.
Partner: UNT Libraries Government Documents Department

Production test IP-750 raw water as a reactor coolant. Final report

Description: Approximately ten years ago single-tube tests demonstrated the feasibility of using unfiltered river water as a reactor coolant from the standpoint of aluminum corrosion and film formation. However, some effluent activity penalty was indicated. Inasmuch as both current water plant operation and the characteristics of Columbia River water have changed, it was deemed appropriate to reinvestigate the use of partially treated water as a reactor coolant. This report summarizes the results of a half-reactor test carried out at F Reactor.
Date: August 10, 1966
Creator: Frymier, J. W. & Geier, R. G.
Partner: UNT Libraries Government Documents Department

Richland five-year 02 R&D program: Co-60 Program

Description: This Cobalt 60 program is part of the Richland five year 02 R&D program. Topics discussed in this summary include incentives, scope and objectives, progress during report period, budget period plans, and an evaluation of progress against plans and objectives. Progress has reasonably paralleled expected results in that megacurie quantities of Co-60 have been secured with activities of 20--60 curies per gram by January 1966 and 100 curies per gram by July 1967.
Date: June 16, 1966
Creator: Bowers, C.E. & Pierick, E.G.
Partner: UNT Libraries Government Documents Department

High pressure, low temperature end bonding of HDS fuel. Interim report

Description: A solid-state diffusion bond is produced at the end bonding step of the Hot-Die-Size (HDS) process as the aluminum cladding is placed in intimate contact nickel-plated uranium core for a finite period of time at an elevated temperature. The combination of these required parameters of time, temperature, and intimate contact (pressure) may be varied within certain limits and still produce a quality diffusion bond. Through nondestructive and destructive testing, fuels end bonded at the higher pressure proved to be of equal quality to those produced under standard conditions. Bond testers indicated no significant difference between test and control fuels. This was verified with bond strengths that were equivalent to those of control fuels. Metallographic data also confirmed the formation of a thinner, apparently more uniform, bond on the test fuels than on the controls. X-ray data that defined the longitudinal growth showed no significant difference between test and control fuels. The objective of the testing covered in this document was to reduce the end-bonding cycle time on the four-station prototype end bonder.
Date: January 10, 1967
Creator: Schweikhardt, G.M.
Partner: UNT Libraries Government Documents Department

Half plant activated alumina test: Final report

Description: A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this possible approach appeared warranted. This report summarizes the results of this test. Samples taken from each effluent riser during reactor operation indicated no improvement in either As{sup 76} or P{sup 32} performance. This comparison is shown below with a complete tabulation of daily values included as Attachment 1.
Date: May 5, 1967
Creator: Pitman, R.W. & Wells, G.W.
Partner: UNT Libraries Government Documents Department

Status of special reactor process tube loadings, January 1, 1966

Description: This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. Data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document RL-REA-837.
Date: January 14, 1966
Creator: Bown, R. W.
Partner: UNT Libraries Government Documents Department

Volume increase analysis of production test 040

Description: This statistical analysis examines volume increase data from PTA-040. The purpose of this analysis is to compare four 1.25 enriched uranium core alloys (Standard, British, High Silicon, and Modified British), two heat treatments (Induction and Salt Bath), and the alloy-treatment interaction. The four core alloys were each processed using the two treatments and then canned as 5.540-in. AlSi fuel elements. Test pieces were charged in 16 tubes with 40 pieces per tube. The eight fuel types (4 alloys {times} 2 treatments) were arranged in a series of Latin squares in the test tubes to eliminate the effect of position and tube. A comparison of volume increase was deemed worthwhile after analyzing PTA-040 with regard to fuel element distortion. Volume increases in the present analysis were calculated by H.D. Huber using OD and ID measurements taken at C-Basin with consideration for can wall corrosion and geometric distortion. these volume increase calculations were not completely substantiated, since a thorough check with water displacement measurements at the Radiometallurgical Laboratory was not possible. Despite this fact, the present analysis was continued since a good correlation between the volume increase calculations and element exposure was observed.
Date: September 5, 1967
Creator: Stein, R.C.
Partner: UNT Libraries Government Documents Department

Status of special reactor process tube loadings, July 1, 1968

Description: This report gives the status of production tests control tube loadings in reactor process tubes containing significant amounts of SS material. Data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-3443.
Date: July 8, 1968
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department

Status of special reactor process tube loadings, June 1, 1966

Description: This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. Data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.
Date: June 8, 1966
Creator: Bown, R.W.
Partner: UNT Libraries Government Documents Department

Status of irradiations performed by testing and irradiation services for BNW as of March 10, 1968

Description: This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Specific data given is TISR No., Request number, Material, Piece number, operating time, CMK Absorbed, charge date, location, exposure to date, discharge date and time, and shipping date.
Date: March 25, 1968
Creator: Barker, L.V.
Partner: UNT Libraries Government Documents Department