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This report discusses the interim program for the production of neptunium oxide at HAPO which applies the following processing steps: isolation of neptunium from the Purex process streams, using Purex flow sheets specially adapted for this purpose; purification of the neptunium nitrate by an ion exchange process carried out in one of the Redox laboratory (222-S) multi-curie cells; and precipitation of neptunium oxalate and conversion of the oxalate to oxide in laboratory-type equipment. The process, being still in the developmental stages, is as yet subject to extreme fluctuations, both conditions and results.

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This report addresses the APPR critical experiment program meeting.

This report discusses current plans of the Irradiation Processing Department which call for the inauguration of an E-metal (0.94% U-235) replacement program for the C-metal columns now in reactor use. Other reactor planning is considering the use of E-metal for E-N (lithium) nd E-Co (cobalt) loadings, compensation for reactor biological shields, and for the improved production reactor (IPR). Activation of any of these plans will be dependent on results of the test programs and A.E.C. policy decisions. The quantity of E-metal that might require separation processing is estimated and an economic analysis is provided

To determine, by test, the feasibility of decreasing the time requirements to prepare the aluminum clad uranium slugs into uranyl nitrate solution suitable for the separation of plutonium from uranium in the extraction step.

The information pertaining to the programs of AEC National Laboratories and other AEC contractors in direct support of the Savannah River project during Fiscal Years 1957 and 1958. The major part of this supporting work we are recommending is associated with the development and the experimental production of extended-surface elements for increasing the Plant productivity of plutonium and tritium. For the first time a portion of this work on the development of extended-surface elements is aimed specifically at increasing their stability and reducing their cost. The total cost estimate of the supporting programs covered in this letter is about $300,000 to $400,00 lower than the cost of such programs in FY-1956. This reduction results principally from the discontinuation of work at Sylvania and Horizons on the development of improved processes for converting thorium nitrate to thorium metal.

Based on the activation of gold foils in an hydrogeneous medium, the neutron flux incident on the rear wall of the discharge area of the KE reactor is estimated to be 6000 M/cm{sup 2} sec. The effective energy of the neutrons is estimated to be approximately 4 Mev. Neither of these values confirm order-of-magnitude estimates of the neutron flux and neutron energy expected to exist in the discharge area.

This document details activities of the irradiation processing department during the month of March, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

Last year (1948) during the flood period the flow at Grand Coulee fluctuated widely. 2 PM, June 8, 543000 c.f.s.; 4 AM, June 9, 568000 c.f s.; 2 PM, June 9, 543000 c.f.s.; 2 AM, June 10, 573000 c.f.s. A total instantaneous fluctuations of 37,500 c.f.s. was reported. Now there is installed a new control. This control can keep downstream variation within 500 c.f.s. By lowering the lake level prior to the crest period, the drum gates could be used as flood control (1948 high water basis) the drum gate control plus the water turbine discharge (if the lake level had been reduced) could have dropped the crest at Richland three feet. a. Drop in crest at Richland one foot: Electrical loss nominal, b. Drop in crest at Richland two feet: Electrical loss 1 megawatt/foot for six generators. Loss Max possible 13,310 KW each generator, 79,860 KW total (7 days). Capacity 1,170,000 KW Max Loss 6.8% for 7 days to 10 days. c. Drop in crest at Richland three feet: Electrical loss 1 megawatt/foot for 6 generators Max possible 30,100 KW each generator 180,600 KW total 8 days. Capacity 1,170,000 KW Maximum loss 15.4% for 8 to 12 days. Actual …

This document details activities of the irradiation processing department during the month of June 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.

The objective of this production test is to determine the changes that occur in the uranium-Al-Si bond during irradiation at bond temperatures between 255 and 285 C. Twenty-five M-388 jacketed dip canned depleted uranium solid fuel elements will be irradiated to an exposure of 500 MWD/T in high temperature water. The location and size of unbonded areas on the fuel elements will be measured by ultrasonic mapping before and after irradiation to show the changes in bonding resulting from irradiation at high temperature.

Two coextruded, Zr-2 clad, natural uranium, seven rod cluster fuel elements were irradiated to a calculated exposure of 1250 MWD/T in the KER Facility and discharged 1-16-59. The fuel elements were NPR candidate fuel and examination was requested to determine the behavior of coextruded, Zr-2 clad, natural uranium irradiated at core temperatures of approximtely 425{degree}C. The elements were transferred to the Radiometallurgy Laboratory 2-25-59. The elements demonstrated excellent in reactor performance with no significant changes in either the fuel or the hardware. Detailed examination of the central rod and two peripheral rods from one of the clusters showed no microcracks in the uranium. Moderate growth was observed in the fuel at the unrestricted rod ends.

The objective of this Supplement described in this report to Pt-IP-250-A is to d enriched tube-and-tube elements will develop pitting corrosion on the Zircaloy-2 jackets when irradiated in pH 10 water. The measurement of dimensional changes in the fuel elements and the observation of the effect of irradiation on the uranium and bond area are also objectives of the test, but secondary in importance to identifying a pitting corrosion problem in NPR quality water, if one exists.

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for September 1956.

The primary purpose of this test was to demonstrate that the inside of a rear-cross-header, its nozzles and pigtails could be decontaminated by recirculating for 30 minutes, a 60{degrees} C, O.3 pH chromic acid solution. Secondary purposes were, (1) to determine the magnitude of radiation increase in piping and acid equipment external to the reactor encountered during the test and (2) to obtain information as to the kind and amount of contaminants removed by the acid solution.

A Task Force was established in the Irradiation Processing Department to examine the K-Reactor Water Plant to (1) review the operating and maintenance experience with the water plant as improved since startup, (2) identify major plant additions which could further improve reliability, and (3) estimate the costs of any such additions. The K-Water Plant basically consists of the electrically driven primary cooling system with power supplied by the BPA system, electrically driven secondary or backup cooling system powered by a steam driven emergency generator pair, and a ``last ditch`` system consisting of hydraulic cross-ties between the two K-Water Plants. This report summarizes information developed in the course of the Task Force deliberations.

This experiment was designed to furnish data on the quantitative relationship between exposure of enriched uranium metal to thermal neutron bombardment and the subsequent release of gaseous fission fragments from the metal. Studies of data obtained from the in-pile phase of the KAPL Fission Gas Experiment indicate, neglecting startup and shutdown transients, that gaseous fission fragments generated within a 6-mill foil of uranium metal maintained at an operating temperature of about 450 C are released from the foil nearly as fast as they are produced.

This document presents a summary of work and progress at the Hanford Engineer Works for May 1953. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

This report covers the preliminary data obtained in a metallurgical study of the three enriched uranium slugs which ruptured in the 100-C Pile. The three slugs were from PT-105-532-A2, ``Irradiation of Enriched Uranium Slugs,`` a test conducted by Pile Technology for the purpose of studying the effects of high specific powers in uranium slugs. The uranium used in this test was enriched to 1.75.

This document details activities of the irradiation processing department during the month of November 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operation; production and reactor operations; facilities engineering operation; employee relations operations; and financial operation.

This is the second of a series of documents issued quarterly. The documents present, for critical examination by management and for the information of related groups, that portion of the future 100 Area technical program which relates directly and more or less immediately to the Technical-Manufacturing efforts to increase both power levels and production. An attempt is made to describe and justify the key production tests planned for the following six month period. Only those tests necessary for the relief of technical and process limitations and vital to the slug improvement program are included. Best estimates of changes in current Process Specifications during the ensuing six months are also given. To further longer range planning, power level forecasts based on foreseeable changes of technical limits and scheduled physical changes of the water plants and reactors are extended several years into the future.