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- Task 1 Nuclear safety study
- No Description Available.
- Metallurgy research sub-section quarterly progress report, October--December 1955
- This quarterly report details activities of the Metallurgy Research Sub-Section for the months of October, November, and December 1995.
- Authorization for change in process 234-5 Building: Argon purging of reduction equipment
- No Description Available.
- Improvements to Task 1 and Task 2 234-5 Building
- In the P234-5 Building operation, Task I consists of converting plutonium nitrate solution received from the primary separations plants to a plutonium oxalate slurry. The slurry is filtered and the filter cake is transferred to Task II while the filtrate is treated and returned for further processing in either Recuplex, Redox, or Purex. The basic Task II process consists of calcining the plutonium oxalate cake to form plutonium dioxide. The plutonium dioxide is then fluorinated to form plutonium tetrafluoride which is transferred to Task III for further processing. Various alternate schemes for increasing production have been studied by the Technical and Design Sections during the past several months. The results of these studies are available in references (10) and (11). It is the purpose of this document to describe in detail the new equipment required for replacing Task I and II and to serve as a basis for detailed design of the proposed project.
- Design and development study: Task 2 replacement RM Line 234-5 Building D.O. 100991
- The Dry Chemistry Process of the RM Line provides the means for converting plutonium oxalate to plutonium tetrafluoride. This process consists of drying the oxalate cake and then converting to the tetrafluoride by passing HF gas at elevated temperature through the filtered cake. Improvement to or replacement of the present Task II system is being investigated because of the high maintenance costs and unreliability of the present system. This study is one of several being conducted under the Chemical Processing and Reduction Design and Development Program for improving Task II operation. This report describes a Task II system using round filter boats and vertical hydrofluorination furnaces.
- Report of the special study group
- The special study group was activated by a charter letter from Sub-Section Managers of Pile Technology on June 20, 1956. The principal objectives were: to collect the information which is presently available for new reactor design and to determine what information should be developed; to make a guess at pile variables; and to point out development programs which must be pursued to achieve a detailed design start in two years. The study was restricted to graphite moderated reactors with H{sub 2}0, D{sub 2}0, and organic coolants. The program was to determine technical feasibility only and detailed economic considerations were not to be included. This report presents the conclusions of the group and some of the reasoning behind these conclusions.
- Production test 234-5-1-MS, Evaluation or use of filter paper in conjunction with filter boats
- No Description Available.
- Critical mass study of 231 process tanks
- An estimated minimum critical mass for each of the process vessels in the 231 Building has been calculated on the basis of critical mass data given in the P-11 Project Document HW-24514. The calculations are made assuming the plutonium to be a homogeneous mixture of precipitate and water with some slight neutron poisoning due to other elements. The precipitate is further assumed to have partially settled making an effectively infinite water reflector above the plutonium and hence reducing the critical mass.
- Plutonium product quality
- No Description Available.
- Nuclear safety limits for the powder recovery hood, room 234, 234-5 Building
- No Description Available.
- Project CG-551, Addendum to basic process and equipment requirements for modification of RMA Tasks 2 & 3-234-5 Building expansion
- No Description Available.
- The isolation and packaging of fission products at Hanford
- Research and development work on the removal of specific fission products from aqueous wastes has been in progress at the Hanford Atomic Products operation for several years. Initially, the primary incentive lay in the safe and economic disposal of these wastes. Scavenging techniques were developed which permitted the precipitation of the long-lived and biologically hazardous fission products cesium and strontium and the subsequent discharge of the supernates to the soil. Recently, interest has increased in the recovery of specific fission products for use in industry. Accordingly, research and development efforts have been expanded to include the search for economic processes for the isolation of specific fission products from Hanford wastes. The processes and techniques thus far developed are logical outgrowths of the scavenging processes currently being used in the disposal of Hanford wastes. The Hanford Operations Office directed a letter of inquiry to the General Electric Company requesting an appraisal of the feasibility of isolating and packaging radiocesium from Hanford wastes. In accordance with this request, the Engineering Department conducted a brief survey to determine the process, engineering, and economic feasibility of recovering specific fission products from Hanford waste solutions. This document presents the combined efforts of personnel from Chemical Research and Chemical Development (Separations Technology Section), Process Engineering (Design Section), and Project Engineering and Project Auxiliaries (Project Section).
- Process test MS-235-5, reduction of Task 3 cooling time, RM line
- No Description Available.
- Production test 234-5-2-MS, Evaluation of the A331 crucible or modification thereof for routine use as a reduction crucible on the remote mechanical line
- No Description Available.
- Natural convection reactor
- A previous report described the conceptual design of a plutonium producing reactor that may be characterized as follows: Power output (2000 MW); cooling - (natural convection of light water through the reactor, up through a draft tube to an evaporative cooling pond, then back to the reactor, and fuel (400 to 500 tons of uranium enriched to 1.2% U-235). Because this reactor would be cooled by the natural convection of light water, it is believed that the construction costs would be significantly less than for a Savannah or Hanford type reactor. Such expensive items as water treatment and water pumping facilities would be eliminated entirely. The inventory of 500 tons of slightly enriched uranium, however, is an unattractive feature. It represents not only a large dollar investment but also makes the reactor less attractive for construction during periods of national emergency because of the almost certain scarcity of even slightly enriched uranium at that time. The Atomic Energy Commission asked that the design be reviewed with the objective of reducing the inventory of uranium, The results of this review are given in this report.
- Analytical research applied research unit, quarterly progress report, April--June 1952
- This quarterly report details activities in analytical research by the Applied Research Unit of the Nucleonics Division during the months of April, May, and June 1952.
- Authorization for process change 234-5 Building
- No Description Available.
- Separations P.E.S. report No. 11: Task 1, activation study, RMA Line 234-5 Building
- It was the purpose of this study to determine whether it will be more desirable when activatiing Task I of the RMA. Line to revise the existing remotely operated equipment or to remove existing equipment and install a manually operated facility. It was also the purpose of this study to provide sketches and cost estimates for each alternative which could be used as a guide for preparation of a Project Proposal. At present, the process to be used in Task I has not been established. This study, therefore, necessarily covers only processes similar to those for which Task I was originally designed. Information received from the Process Unit indicates adoption of such a process is probable.
- Service of reduction bombs, plutonium purification and fabrication 234-5 Building
- No Description Available.
- 234-5 Development summary report: Recovery of plutonium from skulls
- No Description Available.
- Monitoring of direct chemical assay of fabricated parts
- The specification for the plutonium content of fabricated parts requires that for each three-months production a statistical estimate be made of process variance (variation in actual plutonium content from part to part). Prior to the fourth quarter of 1956, this requirement was met by the following indirect technique: Chemical assay was made of at least one-half the parts produced; by-difference analysis (subtraction of the measured impurities from 100 per cent) was made of all parts produced; and the chemical assay and by-difference measurements were analyzed to permit partition of the observed, between-part variance in chemical assay results into process variance and analytical variance.
- Recuplex Feasibility Report
- The recuplex Process is proposed by the Process Assistance group of the Separations Technology Unit as a feasible method for the simultaneous and efficient recovery of waste materials in the 234--5 Building and direct coupling of the product steams from the Redox and Bismuth Phosphate Processes to the 235-5 Building operations. Demonstration of the feasibility of the process has been accomplished through the cooperative efforts of the Chemical Research, Chemical Development, and Process Assistance groups of the Separations Technology Unit and LTS described in this document.
- Chemical research quarterly report, October--December 1951
- This quarterly report details activities of chemical research by the Separations Technology Unit for the months of October, November, and December 1951.
- Magnesis specifications and estimated quantity of magnesia in the 234-5 Building Crucible Shop
- No Description Available.
- Critical mass calculations for the recuplex installation
- The methods of an analysis of the critical safety of process tanks in the Recuplex installation are discussed and results of the analysis are tabulated in this report. A minimum critical condition for a thermal chain reaction is estimated for 0-200 MWD/T Pu and for 400 MWD/T Pu for each tank in the installation vhich normally contains, or could contain, plutonium. All estimates are based on experimental critical mass data from the P-11 project and from Oak Ridge critical mass experiments.
- Nuclear safety limits for the powder recovery hood, room 234, Building 234-5
- No Description Available.
- Critical mass studies of plutonium solutions
- The chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders. The effects on the critical mass of the displacement of hydrogen and the addition of poisons to the fuel were measured in water tamped and bare reactors. In this report the data obtained in the investigation is presented graphically and in tables. Some preliminary analysis has been made yielding the results: (i) the absorption cross-section of Pu{sup 240} is 925 {plus_minus} 200 barns and (ii) the minimum critical mass of Pu{sup 239} in water is 510 grams at concentration of about 33 grams per liter.
- Survey of required equipment charges for RMA and RMB lines, 234-5 Building, incurred by model changes
- No Description Available.
- Authorization for use of an alternate method of processing turnings: 234-5 Building, briquetting of plutonium turnings
- Plutonium turnings formed in the machining operation are processed by recycling them to the reduction operation. The turnings are here combined in the radiation charge to form a button with the plutonium from the reduction of the fluoride. Occasionally an inventory of turning will accumulate, especially when a number of machined pieces are recycled to be recast. Since the amount of turnings to plutonium in plutonium fluoride considered safe for reduction is a maximum ratio of 1.35, a high turnings inventory can only be expended at a limited rate. Briquetting offers a convenient way of depleting the turnings inventory in a rapid manner. A total of twenty-four briquettes were pressed. Eight castings were made by casting three briquettes into a form suitable for further processing. Six of the eight castings were accepted at final inspection. One was too small to machine due to an interrupted heating cycle and the other was recast after two coating failures with subsequent stripping caused the piece to be out of specifications in size. Castings made from briquettes were comparable with those made from buttons in parity, homogeneity of the alloy, and lack of voids. Skulls from the casting of briquettes varied form 10 to 11 per cent of the weight charged as compared to normal skulls of 2 or 3 percent of the weight charged when buttons are cast. Because of the large skulls, briquetting is not as efficient as recycling the turnings to the reduction operation.
- Statistical study of variations in yield. 234-5 Building Reduction Operations
- This study was made to evaluate the effects of several operatin variables on the yield at the reduction step in motel fabrication. The original question was whether or not the addition of recycled metal to the charge had an effect on the yield. To circumvent possible masking of such as effect by changes in other operating factors, simultaneous data on the weight of Pu in the powder charge, the % conversion of the powder to PuF{sub 4} in the fluorination step, the firing time, and the maximum temperature were also studied. This permitted estimation of the separate effects of al five factors. The period covered by the data was October through December, 1950.
- Nuclear safety 234-5 Building
- This report contains notes and calculations regarding safety of the 234-5 Building.
- Radiation studies 234-5 Building No.7: Sensitivity of nuclear track film to Pu-F neutrons
- The results of theoretical calculations regarding the sensitivity of the NTA emulsion to both Po-B and Pu-F neutrons were described in an earlier report. The purpose of this report is to describe the results of an experiment which was performed to verify these values. Data relating to both the sensitivity and the amount of fading which takes place prior to developing were obtained.
- Application of neutron monitors to process control in Recuplex. Status report
- A program was. initiated early in 1957 to develop a neutron monitor capable of detecting plutonium (Pu) concentration in process vessels in Recuplex. This followed an earlier application by Finished Products Operation and Research and Engineering of neutron monitoring to powder counting which had been successful and was being regularly used. The process vessel monitoring was to be done by the ``in tank probe`` method, utilizing the monitored solution as its own-moderator, and detecting the resulting slow and thermal neutrons with boron trifluoride (BF{sub 3}) type proportional counters. This report is intended to present the history of the Recuplex program; a summary of the development work to date; the current status of the monitoring system; and the immediate plans for future installations and work. This report is intended as a design guide for presently scheduled and future monitor installations in Recuplex and elsewhere of the types herein described. The report also includes calibration curves for both D-11 tank and H-3 column monitors, schematic representation of all installations, manual switching panel circuit diagram, pre-amplifier circuit diagram, probe well designs, and Kl-2 instrument tank design.
- Production Test 231-10 Supplement B process evaluation-production of concentrated plutonium nitrate solution in Building 231: Transfer to and processing in Building 234-5. Final report
- All of the 231 Building final product was prepared for off-site shipment prior to the startup of the 234-5 Building. The evaporator (S-1) effluent, a solution approximately 10 molar in nitric acid with plutonium concentration of 275 grams/liter, was dried within the shipping container (sample can) to a solid cake. The purpose of this drying operation was to minimize personnel contamination and/or loss of product during shipment. The dried cake was redissolved in water before further purification steps could be performed. The procedures for testing the purification of AT solution as recommended by the development group (6) were presented in Production Test 231-10 Supplement B. Production Test 231-10 Supplement B was initiated to establish the procedures for the precipitation of Plutonium (III) Oxalate in Plant equipment from AT solutions. The current report is written to provide a history of: Work done and data collected during the test, and Conclusions and Recommendations obtained from studies of the data.
- Rover Test Site
- This report, dated January 9, 1956, provides a discussion of facilities needed for the ROVER project.
- Report of the Chief of the Forest Service: 1952
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1950
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1951
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1953
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1958
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1957
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1956
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- Report of the Chief of the Forest Service: 1955
- Annual report from the U.S. Department of Agriculture Forest Service describing activities of the organization, expenditures and receipts, and a discussion of other relevant topics for the fiscal year.
- The Preparation and Properties of Mammalian Ribonucleic Acids
- "A method for the preparation of mammalian ribonucleic acids employing high concentrations of guanidine hydrochloride in the fractionation procedure is reported in this paper. Aside from the facility of preparation the method has the advantage of avoiding conditions of acidity and alkalinity which might degrade tissue ribonucleic acids and, by virtue of the protein denaturant action of guanidine salts, of minimizing the possibility for enzymatic degradation" (p. 3).
- Liquid Metal Fuel Reactor Experiment: The Economic Comparison of a Large-Scale LMFR Breeder & Burner
- Results of a study to compare economic factors of of burner- versus breeder-type liquid metal fuel reactors. The study takes into account several pertinent criteria and factors to ensure that the reactors would be reasonable to implement.
- Liquid Metal Fuel Reactor Experiment (Phase 1C): Supplement to LMFRE Reference Design Report
- This supplement describes a number of modifications to the Liquid Metal Fuel Reactor Experiment (LMFRE), including (1) engineering design changes to achieve economies in the original reference design, and (2) a revised cost estimate that reapportions the various construction, research and development, and operating costs in accordance with procedures established by the Atomic Energy Commission.
- Nuclear Merchant Ship Reactor Shield Design Summary Report
- Abstract: "Most of the Nuclear Merchant Ship Reactor (NMSR) shield design work performed by The Babcock & Wilcox Company (B&W) is summarized. Primary and secondary shield results are presented, consistent with contractual requirements and designated design criteria. Methods of calculation and basic parameters are shown" (p. 1).
- Enrico Fermi Fast Breeder Reactor Plant
- This report contains a description of the reactor plant portion of the Enrico Fermi Atomic Power Plant, with emphasis on the reactor system. Since this plant contains a developmental reactor, emphasis has been placed on reactor safety and on achieving reliable operation. The design is conservative and is flexible enough to permit incorporation of the results of developmental programs, which include nonnuclear, full-scale component test facility operations, and nuclear experiments, such as critical experiments.
- Method for the Routine Absolute Intensity and Energy Measurements of Beta Radiation; Application to Naturally Radioactive Potassium, Rubidium, Rhenium and Lutetium
- Photocopy of a dissertation discussing natural radioactivities and half life of potassium, Rubidium, Rhenium, and Lutetium.
- Transistors: Counters
- Abstract: "Two transistor plug-in decade counters are described, one of which operates over the SCS-7 temperature range. A transistor digital scanner with storage and parallel readout is described. It utilizes one of the plug-in decades. A simple design procedure for flip-flops is presented."