Information is presented concerning coated fuel particle development and evaluation; burnup capabilities of Y/sub 2/O/sub 3/-stabilized UO/sub 2/ and stabilized fuel - BeO matrix materials; high-temperature studies of substoichiometric urania and urania solid solutions; high-temperature carbides and borides research; and high-flux reactor materials gaseous fuels research.

This report details activities of the Irradiation Processing Department during the month of May 1964.

This document details activities of the Irradiation Processing Department during the month of June, 1964. 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 monthly report for the Hanford Laboratories Operation, December 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.

The monthly report for the Hanford Laboratories Operation, March 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operation, and programming operations are discussed.

The monthly report for the Hanford Laboratories Operation, August 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.

A series of three experimental tests was conducted on the operation and adequacy of the K-Reactors` third, or last-ditch, cooling system. The first test showed considerable line corrosion the second test was performed directly after line cleaning, and the third test showed a significant amount of additional line corrosion after only nine months of service. The present cooling adequacy of this last-ditch system at the KE and KW reactors is summarized these show the power levels for which we have adequate last-ditch cooling as a function of the crosstie coolant temperature. These figures include the effects of increasing the number of pumps that remain in operation at the other K-Reactor, and various other operating or emergency conditions. These curves are for diesel pump speeds of 750 rpm which are planned for June of this year. In these figures the crosstie temperature is assumed to be a conservative 5{degrees}C above the process water inlet temperature.

This is the monthly report for the Hanford Laboratories Operation, November 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research.

This is the monthly report for the Hanford Laboratories Operation, April 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

This report describes EG&G activities in support of the Rover Program for the month of January, 1964. Details are discussed in succeeding sections and in the appendices with respect to the various tasks included in our scope of work. At Test Cell A., the Facility Mapping Test, EP-IV, was success- fully completed. Preparation continued for the NRX-AL program scheduled for February, 1964. At Test Cell C., a high flow acoustics test, EP- 1, was conducted. This was the last experimental plan to be completed before the Kiwi-B4D cold flow test series, scheduled to begin on 31 January 1964. Cost curves, except for Test Cell C Operations, still are somewhat below the budget.

Activities for each of the following departments are discussed in this report: Reactor and Materials Technology Dept.; Physics and Instruments Dept.; Chemistry Dept.; Biology Dept.; Applied Mathematics Dept.; Radiation Protection Dept.; and the Test Reactor and Engineering Services Dept.. Activities are in support of Hanford reactors (production reactors, N-reactor, PRTR reactor, etc) and reprocessing and radioactive waste management efforts at Hanford.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Whether a corporation may, through a non-lawyer, seek a writ of sequestration in a Justice of the Peace Court, or in a Small Claims Court.

This report presents the results of a recent analysis to determine if there is a practical method for using carbon dioxide for pH adjustment at the 100-K Reactors. Carbon dioxide could be recovered from the boiler stack gas and introduced into the K Reactor process water. The approximately $240,000 installation cost would be repaid in about one year by the reduction of sulfuric acid costs. The proposed system would consist of a blower, a purification system, and a distribution system for conducting the gas from the boiler house stacks to spargers in the process water clearwells. The blower would draw gas from the boiler stacks and then blow it successively through the purification system and the distribution system. The purified gas, consisting primarily of carbon dioxide, oxygen, and nitrogen, would bubble up through the water in the clearwells, where the carbon dioxide would be absorbed by direct contact with the water. The development work necessary before the use of carbon dioxide can be recommended consists primarily of in-reactor single tube tests followed by a half-reactor test. These tests are necessary to show the effects of carbon dioxide on aluminum corrosion, effluent activity, and reactor hydraulics. The single tube tests already …

The hot die sizing (HDS) process is being considered as a replacement for the existing AlSi brazing process. Fuel cores are clad by passing a preheated core-component assembly through a die to bond the outside surface. Concurrently, the assembly is passed over a die plug to bond the internal surface. End bonding is accomplished in a following step by applying heat and pressure to the sized fuel element. Remaining fabrication steps are essentially the same as those used for AlSi brazed fuel. Initial irradiation tests indicated that hot die sized fuels experienced in-reactor growth behavior which differed from that of the matched AlSi fuels in the tests. Presently, two tests are being irradiated in the reactor for determining the effect of end-bonding method, and end-bonding pressure in combination with fuel core geometry, upon fuel element diametral growth during irradiation. Due to the length of time required for irradiation and examination, a third test to determine the effect of core heat treatment and stress relieving has been prepared and is ready for reactor charging. This report summarizes the fabrication of oil and water-quenched cores pretreated by both alpha annealing and AlSi brazing for {open_quotes}Production Test IP-708-A, Evaluation of Oil Quenched Hot …

Each of the 25 monitor tubes at B and D reactors have been gauged four to six times since they were installed in late 1961 or early 1962. Since October, 1962, the WTG data indicates the average corrosion rate, is 0.25 to 0.30 mils per month. The corrosion rate of the thinnest tube is about the same as the average tube. As expected, the corrosion rate is low and believed to be a measure of top-wall corrosion. It is estimated that it will take approximately one more year (at 6.6 pH) before the bottom wells will have the same average minimum wall thickness as the top walls. During this period, the main problem will be to determine whether the top wells will continue corroding at rates between 0.25 to 0.30 mils per month. it is recommended the 25 tubes at B and D reactors be gauged with the WTG every metal cycle during the coming year. The Process Engineer will continue to analyze the WTG data as it accumulates and recommend further monitoring or replacement, subject to the details authorized in the parent test.

Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.

Candidate canning materials were tested in contact with molten stand-ins for Pm metal; nondestructive tests were conducted. Related studies included americium processing, uranium-233 support, Ce-Pm separation, and technetium analyses.

This is the monthly report for the Hanford Laboratories Operation, May 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

Instrumentation studies and the Hazards Review have demonstrated the need for instrumentation which will scram the reactors if the exponential rate of power increase is excessive. A development program has demonstrated the feasibility of such a system. This document defines the program necessary to provide Intermediate Range exponential rate protection in the safety circuits of five reactors, provides justification for the project, and presents estimates of the cost and schedule required to accomplish the program.

The monthly report for the Hanford Laboratories Operation, September 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operations are discussed.

In conjunction with the proposed thorium target element replacement program, hydraulic tests were performed in the Hydraulics Laboratory in 185-D building to determine the flow characteristics of 1.480-inch OD solid thorium loadings in B, C, D, and K fringe tubes. Included are supply curve data for those orifice combinations which are tentatively to be used with the thorium loads in the various fringe tubes. In addition, predicted supply-demand characteristics are presented for a loading of 1.600-inch OD thorium solids in a K-Reactor Zircaloy-2 process tube equipped with a 0.270-inch flat-plate orifice in a X central zone double-orifice retainer union (cage), Drawing H-1-21952.

Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.

Introduction: It is the purpose of this report to describe the operating and maintenance experience obtained at HNPF on the sodium heat transfer pumps.

Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.