Aid in redesign of the calibration facility in order to: 1. Reduce the rate of exposure for calibration personnel below 1 mr/hr; 2. Reduce the rate of exposure outside of the 3745 Building; 3. Reduce the risk of breaking radium sources; 4. Improve the efficiency of calibration procedures by: a. Allowing calibration to be done faster; b. Providing several calibration ranges which can operate simultaneously in the present space allowed; c. Allowing instrument survey work to proceed while calibration work is done. A well-type calibration installation is proposed and a brief description of the required shielding is included.

Porous alundum filter plate samples were received for testing to determine the effects of Redox process solutions and conditions on bend and impact properties. Alundum has been suggested as a barrier material for use in the Redox Silica Gel Absorption Column T-101. Consequently, data on possible engineering property changes caused by exposure to separation process solutions and radiation are needed to evaluate the applicability of alundum as a barrier material.

In the following report the effective radii of infinitely long cylindrical control rods of various radii and blacknesses have been calculated. The results are given in a graph at the end of the report.

The preparation, purification and chemical properties of TBP have been reviewed with emphasis on the hydrolytic reactions. The latter is supplemented by data on other alkyl phosphates.

One of the problems associated with evaluating the hazards resulting from the discharge of radioactive pile coolant water into the Columbia River results from the subsequent consumption of the river water by cities downstream of Hanford. Determination of the travel time of the river water from the reactor cooling water discharge points to the first downstream cities to consume the river water (Pasco and Kennevick) is a necessary part of the hazard evaluation. Knowledge of the travel time is required to establish decay correction factors for river samples collected in the Regional Monitoring Program and to determine the correct sampling time at downstream locations for samples that may represent specific Hanford operating conditions.

In the Purex process, nitric acid is recovered from aqueous wastes by concentration and rectification. The concentrator bottoms are relatively corrosive to stainless steels, particularly on heat-exchange surfaces. This report summarizes studies aimed at determining corrosion rates for certain candidate materials of construction (304-L, 347, 312 stain steels and A-70 titanium) for the aqueous waste concentrators. Synthetic Purex Process 2WW, representing bottoms from the low level waste concentrator, was used as the corroding medium. Purex Process flow sheet changes made since this work was started have resulted in some changes in the compositions of the aqueous wastes. Consequently, data reported here are representative of, but perhaps not precisely, those which would be obtained using the present 2WW composition.

The special x-ray photometer was designed to measure various characteristics of high-absorption materials by comparing the attenuation of an x- ray beam in passing through a sample of known size with the attenuation through a standard. A general description, discussion of elements, safety features and cautions alignment and adjustment, and operation and maintenance are presented.

Dimensional instability was one of the first difficulties encountered with uranium fuel elements. Early in the operation of the HAPO reactors it was found that uranium fuel elements changed shape as a result of having been irradiated. This problem of dimensional instability has been vigorously pursued up to the present day.

The scintillation alpha counter was further developed to produce better long-term reliability and ease of maintenance.

A new method to process uranyl nitrate solutions for the production of useable compounds for subsequent reduction to metal is suggested.

In the Columbia River downstream from Richland, Washington there is a gradual decrease in the concentration of radioactive isotopes. At any one location there are fluctuations due to factors such as ditution and decay time. During this period at all locations the concentration of alpha particle emitters in water averaged below the detection limit of 3 x 10⁻⁹ μ c/gm. Beta particle emitters in water upstream of McNary Dam increased by a factor of 1.5 to 2, with averages at various locations ranging from (3 to 40) x 10⁻⁷, but in river mud the average of 2 x 10⁻⁵ μc/gm was about 2/3 that during the previous quarter. Downstream from McNary Dam, beta particle emitter average concentrations in water were about the same as those during the past three quarters.

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.

Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.

Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.

Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.

Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.

The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.

This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.

Report describing a series of tests performed to review the safety procedures and systems of Hanford Laboratories' N-Reactor.

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In addition, the development of strontium-90 as a major product requires increased flexibility in the utilization of these casks.