Criminal intelligence report to Captain W. P. Gannaway and Lt. Jack Revill concerning William Earl Patrick O'Donnell. The report includes two photos of Mr. O'Donnell.

The original test authorized the irradiation of about 20 fuel columns containing hot-die-sized, diffusion-bonded fuel elements. Objectives of this supplement are to permit irradiation of an additional ten columns of hot-die-sized, diffusion-bonded fuel elements, and to obtain data on the relation of the coolant temperature distribution and fuel element behavior. These fuel columns will be irradiated in smooth-bore Zircaloy-2 process tubes in the C Reactor.

Data in this report are significant to Pile Physics calculations and are submitted by the Area Physicists at the respective reactors. Reactivity in non-uranium charges and in radial and spike enrichment is calculated either by one-group diffusion theory or by the simpler flux-squared weighting method. The former method provides a more accurate evaluation for larger enrichment inventories; the latter method is sufficient for radial enrichment of less than about 0.25 percent excess K.

This document provides a method for calculating the compensating effects of horizontal control rods in highly shadowed cases encountered in total control administration. The two-dimensional diffusion theory computer code ``9 ANGIE`` was used to calculate the reactivity effects of the horizontal control rod geometry with respect to total control requirements at B, D, F, and DR Reactors. For total control requirements in the center section of B, D, F, and DR Reactors the horizontal control rods will compensate approximately 25% of the buckling increase presently due to enriched fuel at the top and bottom of the pile. If the enrichment is already compensated by adjacent supplementary poison, the inserted horizontal control rods will reduce the center ``B`` section buckling by an amount equivalent to charging 2 PCCF tubes in the center zone. The direct compensating effect of the horizontal control rods with respect to the enriched fuel on the near side of the ``square pile`` remains unchanged.

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. Three channels of IRATE (Intermediate Range Automatic Trip Equipment) should be installed in the two K and three small reactors., and incorporated into the Number 1 Safety Circuits. Each channel should sense the output of its own gamma-compensated ion chamber located in the thermal shield of the reactor. A two-out-of-three channel coincident trip circuit should be used in the safety circuit. GE should manage the program and develop the specifications for the engineered equipment. Procurement should be by competitive bids to GE`s specifications and drawings. The proposed program is estimated to cost $520,000.

This document reports the IPD production projections and reactor inventories for Hanford C and K reactors. Tables included contains the following information: Operating efficiency, exposure, conversion ratio, tonnage, production, and power level.

The first series of tests in the C-1 Loop was designed to test the corrosion characteristics of several aluminum alloys at coolant temperatures up to 290C. Details of the test are documented elsewhere. Four fuel assemblies were irradiated. This report sizes the operating history and the pertinent test data for each of these assemblies.

The gas-pressure-bonding process is being evaluated as a means of fabricating tungsten-UO 2 hexagonal-celled fuel geometries. A two-part study was initiated to optimize the fuel materials and to develp the required fixturing and loading techniques. Production of fueled tungsten-coated UO 2 particles in in progress so that geometries embodying coated particles or coated particles plus fine tungsten powder can be evaluated. Tests to data have shown the rquirement for a pretreatment in which a gaseous oxide phase is removed. Initial loading and fixturing procedures were proven satisfactory by the fabrication of a 19-cylindrical-hole hexagonal-type composite.

Over the past two years a number of programs have been initiated that have introduced several variables to the production scene which can significantly influence Hanford dissolver capacity. The more important of these are the utilization of recovered acid for dissolution, the development of I and E fuel elements, and the advent of direct-casting methods for fuel element fabrication (dingot metal). Evaluation of the relative status of dissolution capability with potential production requirements has as a result become somewhat more complex due to the increasing difficulty of weighing the effects of the various parameters involved. It is the purpose of this report to present most of the details, relevent to dissolver operation, that are necessary for capacity evaluation, and from which conclusions as to dissolver adequacy can be drawn with reasonable confidence.

From Scope of Investigation: "The work reported here is part of a continuing program concerning the long-term volume changes in concretes made from lightweight and normal-weight aggregates. The creep, drying-shrinkage, and strength data presented are for concretes made with 24 expanded shale lightweight aggregates and 5 natural, normal-weight aggregates. These aggregates were from widely separated geographical locations and were to be representative samples of aggregates being used in the production of structural concretes."

Intelligence report addressed to W. P. Gannaway of the Dallas Police Department's Special Service Bureau. The report, which was submitted by detectives W. S. Biggio and L. D. Stringfellow, regards an interview with Eugene Dibbles. Dibbles stated that Jack Ruby did not come into the Allright Parking Garage on November 24th, 1964.

Intelligence report addressed to W. P. Gannaway of the Dallas Police Department's Special Service Bureau. The report, which was submitted by detectives W. S. Biggio and L. D. Stringfellow, regards an interview with Eugene Dibbles. Dibbles stated that Jack Ruby did not come into the Allright Parking Garage on November 24th, 1964.

Intelligence report addressed to W. P. Gannaway of the Dallas Police Department's Special Service Bureau. The report, which was submitted by detective P. M. Parks, states that William Earl Patrick O'Donnell last worked at Western Gear Corp. and was previously charged with burglary.

Intelligence report addressed to W. P. Gannaway of the Dallas Police Department's Special Service Bureau. The report, which was submitted by detective P. M. Parks, includes mug shots of William Earl Patrick O'Donnell from 1949.

Photocopy of a report addressed to W. P. Gannaway of the Special Service Bureau in Dallas, Texas. The report, which was submitted by detective P. M. Parks, is illegible. Documents from the United States Department of Justice are attached to the report.

State of Texas Corporation Franchise tax return of 1963 for United States National Company. The return includes all necessary schedules and financial statements.