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Richland five-year 02 R&D program, plutonium-238

Description: There are three principal facets to the Pu-238 Program which are important to Richland. First, reactor neptunium production rates can be materially enhanced by judicious fuel management plans. Second, significant improvement in production efficiency and costs can be made if the Pu-238 production step (irradiation of Np-237) were sited at Richland. Further, Richland reactors have ample capacity, without reducing power, to irradiate all neptunium from government and commercial reactor sources which has been forecasted well into the 1980`s. Third, a separate Pu-238 production process, that of irradiating Am-241 (obtained from power reactor plutonium returns), offers an attractive and competitive means to materially supplement Pu-238 from the Np-237 route. The first two of these aspects of the Pu-238 Program are being pursued actively, particularly in light of firm and predicted requirements for Pu-238. Technological development for irradiating and processing Am-241 will be carried out in the near future.
Date: June 1, 1967
Partner: UNT Libraries Government Documents Department

Summary Evaluation of Conceptual Design for 50 MGD Desalination Plant

Description: Report issued by the Office of Saline Water discussing the conceptual design of a 50 MGD water desalination plant. Numerous design concepts are presented, along with detailed descriptions and comparisons of the different designs. This report includes tables, and illustrations.
Date: August 1967
Creator: Hunter, J. A.; Sieder, Everett N. & Tomalin, Paul G.
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

Thickness of Bituminous Coal and Lignite Seams Mined in 1965

Description: Report issued by the Bureau of Mines discussing the thickness of coal seams mined in the United States between 1945 and 1965. Locations, and production of coal seams are presented. This report includes tables.
Date: August 1967
Creator: Young, W. H.
Partner: UNT Libraries Government Documents Department

Status of irradiations performed by testing for BNW as of May 14, 1967

Description: This report itemizes the irradiations performed by Testing for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.
Date: June 6, 1967
Creator: DeMers, A.E.
Partner: UNT Libraries Government Documents Department

Long range plan - Plowshare excavation program (Book 1 - 1966/1967 excavation program binder)

Description: The purpose of this report is to present a proposed five-year program for the Plowshare Excavation Program. In preparing this study we proceed as follows: (a) Review the significant advances (since 1963) in nuclear excavation technology, and (b) identify the key uncertainties in that technology. After completing these two steps, we then proceed to identify key experiments and any new measurements that may be required to increase our predictive capability and/or to resolve the major uncertainties. It is probably clear that if one proceeds in this fashion one may not necessarily arrive at the existing long range excavation program (e.g., the definitions of experiments beyond Cabriolet and Buggy). In fact, one might expect to derive a significantly different long range plan.
Date: September 7, 1967
Creator: Knox, J. B.
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

Plowshare program goals

Description: This memorandum describes the goals for the fourth quarter of fiscal year 1967, for the Plowshare Program. The goals are set out as minimum goals to be achieved by different divisions in the laboratory which are involved in this program. Some of the direction depends upon whether a preliminary test explosion is fired.
Date: March 13, 1967
Creator: Werth, G.C.
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 irradiations performed by testing for BNW as of June 11, 1967

Description: This report itemizes the irradiations performed by Testing for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.
Date: June 29, 1967
Creator: DeMers, A.E.
Partner: UNT Libraries Government Documents Department

Pacific Northwest Laboratory Monthly Activities Report, Division of Production and Hanford Plant Assistance Programs: March 1967

Description: This document is a Pacific Northwest Laboratory Monthly Activities Report for March 1967, for the Division of Production and Hanford Plant Assistance Programs. Included in this report are brief status reports on the following programs: (1) Direct AEC Sponsored Programs including Columbia River studies, whole-body measurements of Richland school children, field tests using the U{sup 235} Analyzer, and criticality studies (2) Assistance to Douglas United Nuclear including transducer development studies, design of a simulated fuel column, and process technology (3) Assistance to General Electric N-Reactor Department including various fuel element studies, N-process tube scratching studies, and other reactor-related tests and simulations (4) Assistance to Isochem including experimental studies on corrosion, separations instrumentation, etc. and (5) Technical Assistance to the Hanford Plant including programs on environmental evaluations, dosimetry studies, and instrumentation services.
Date: April 1, 1967
Partner: UNT Libraries Government Documents Department

Douglas United Nuclear, monthly report, March 1967

Description: This document contains information about the activities of Douglas United Nuclear at the Hanford site during the month of March 1967.
Date: April 14, 1967
Partner: UNT Libraries Government Documents Department

Hupmobile cloud chamber parameters

Description: The accompanying table lists the presently selected parameters for the twelve cloud chambers. The chambers are numbered consecutively from 4 through 15 as they are lined up in the bunker. The lowest number is closest to the source. All except the first chamber have some thin metal filters to attenuate the flux and harden the spectrum. Cloud chambers 10, 12, and 14 are shielded by a collimator with about 200 pinholes in it. The flux in these chambers is attenuated by the ratio of the pinhole area to total beam area which is a factor of 50. Various gases and gas pressures are used to obtain suitable track lengths and interaction cross sections. Neon, argon, and krypton are used to obtain photo electrons. Hydrogen is used to obtain Compton electrons.
Date: September 28, 1967
Creator: Hansen, N. E.
Partner: UNT Libraries Government Documents Department

Post-piledriver re-entry

Description: This report details post-Piledriver Re-entry. Re-entry down the Piledriver shaft went slowly. The shaft collar had bounced so high and hard that there was a separation directly under the collar and approximately 30 feet vertically of shaft wall in that area spalled off and fell into the skip Docket. The collar area had to be packed with new concrete prior to advancing further downshaft. Drilling, sampling, gas analysis, and radiation monitoring activities are detailed.
Date: November 17, 1967
Creator: Rabb, D. D.
Partner: UNT Libraries Government Documents Department

The cloud chamber as a field diagnostic tool

Description: This document presents the Pros and Cons of using a cloud chamber for field use. Historical aspects are briefly discussed. A cloud chamber experiment on Midi Mist is described. Plans for fielding an experiment on Hupmobile are presented.
Date: October 19, 1967
Creator: Clark, A.
Partner: UNT Libraries Government Documents Department