Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1965, activities, public relations, finance, organizational leadership, and other information about scouting programs.

A report regarding variations in isotopic abundances of strontium, calcium, and argon and related topics

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This report analyses the crude oils from many oilfields within the U.S.

The amino acid and lipid analysis on blood and liver and the amino acid analysis on urine gave irregular values for each determination. Therefore, the average values which were presented in the 1966 Technical Progress report (C00-1449-2) were not considered valid and were not submitted for publication. However, experiments on the in vivo conversion of 75 Se-labeled selenite-Se to urinary metabolites led to the observance of an unknown metabolite. This metabolite, which was different from the ordinary selenium analogues of sulfur, was designated as "U-1" (C00-1449-3). The use of the 59 Fe was involved in the study of the anemia of chronic selenium toxicity. The findings because of the labeled iron led to the conclusion that the anemia was from massive hemolysis (C00-1449-3).

The Atomic Energy Commission contract AT(11-1)-1468, for which this report is presented helps to support a program of nuclear physics research at the University of Arizona. This program utilizes a 2 MV Van de Graaff generator and associated facilities of the University. In addition, construction of a building to house a 6 MV Van de Graaff is underway. In the following sections, progress during the past year is reported, and a proposal for operation during the coming year is presented.

The motivation for an interactive computer system is to obtain fast response for program generation, debugging, and running. The human user retains control of the computing process, and can modify program, change parameters, and correct errors as required during solution of the problem. An interactive system contains a man-computer interface as a distinguishing characteristic. This interface is not present in the more common, batch process, computer systems.

Direct AEC sponsored programs report that: a new mathematical simulation model to handle reactor effluent dispersion was started, final arrangements were concluded for the proposed test of the effectiveness of activated carbon for inorganic ion removal at the Richland Water Plant, the whole body counter used to measure the burdens of radionuclides in Richland school children is being calibrated for persons of small size and with different weight to height ratios; controlled intake of oysters that have accumulated zinc-65 is being used as one phase of this calibration. Assistance to Douglas United Nuclear is reported for missions 1, 10, 11, 13, and 14. Topics discussed here include: diffusion bonding of nickel-aluminium, PCTR experiments, code development, aluminium jacketed uranium fuel elements, and radiochemical analysis of radioarsenic in effluents. The General Electric N-Reactor department reports on:analysis and theoretical interpretation for ice and water, radiometallurgical examination on Al canned targets containing ceramic cores, inspection of irradiated zircaloy-2 clad fuel rods,resonance absorption cross section calculations, and visual inspection of Inconel steam generator tubes. Isochem reports on: dissolution of zircaloy studies, subcritical neutron interaction experiments, carbon monoxide disproportionation on exposure to bismuth oxide, dissolution rates of British alloys in nitric acid, Sr and rare earth …

The purpose of this report is to: establish the existing maximum flow capabilities of B, C and D Water Plants, determine the limiting factors under existing flow conditions and, develop a systematic plan, including scope cost estimates, for removal of limitations which can be accomplished without major expenditures.

In fulfillment of a request by the Atomic Energy Commission, an inspection system was developed by the Hanford Atomic Products Operation of General Electric Company during 1964 for periodic monitoring of production reactors should they be shut down under international agreement. Ground rules included access to the reactor building and to the reactor core itself for installation, checking, and removal of equipment for determining whether or not the reactor had been operated between periodic inspection visits. Subsequent correspondence from the Atomic Energy Commission indicated that the in-core system proposed was satisfactory for the ground rules under which it was developed, but that the Arms Control and Disarmament Agency wished also to know whether or not a perimeter inspection system would be feasible. For purposes of this study ``perimeter`` access at a radius of one mile was to be assumed. Hanford was asked to investigate and report on the feasibility of such a system, the extent of work to be equivalent to a Title 1 design effort. This report describes the work carried out by Battelle-Northwest on this program.

This document is an inventory of the nuclear materials held on site at HAPO.

This document reports on: direct AEC sponsored programs (mainly Columbia River studies and exposure mechanisms), assistance to Douglas United Nuclear (production reactors), assistance to General Electric N-Reactor department, assistance to Isochem (processing), assistance to Hanford occupational health foundation, and technical assistance to Hanford Plant (environment, dosimetry).

This is the second semiannual issue of reactor and power operations data for the Hanford Production Reactors. Summary data from the first issue (1) are repeated for comparison. Experience during each succeeding six months period will be added to these data in later reports until two full years of operating experience are shown. For comparison purposes, the two years of experience will then continue to be shown by dropping and adding a six months period with each semiannual issue. This report is for the period ending June 30, 1966.

This report for June 1966, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.

The PMACS `reactor-normal` signal signifies that important process variables do not exceed their set points, that various interlocks are properly set, that functional tests of the computer operation are satisfactory, and that the reactor flux level and period derived from two additional, independent, and dissimilar channels are within set limits. This safety circuit combines the features of redundancy, dissimilar components, and frequent testing which are required for best reliability. The experimental equipment auxiliary to the reactor includes two oscillator mechanisms, one to move the test cell or the adjoining cell into and out of position, the other to move small specimens in the test cell or adjoining cells. They have cooling chambers for the removal of specimens from the test cell without the necessity of cooling the reactor. A neutron chopper and time-of-flight spectrometer are provided; the neutron detectors, at the end of a 25-meter flight tube, are in an adjoining small building. Test cores may be assembled on a core dolly have a load capacity of 14,000 lb. Two wire traverse mechanisms are provided for measurements of flux distribution.

The plutonium production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as coolant on a once-through basis. Thus, radionuclides formed largely from the activation of river salts are released to the river. In addition to the radionuclides, heat and other chemicals are also added to the river by the reactor effluent. These discharges give rise to a program which includes three separate and distinct areas of study. The first involves devising practicable methods of reducing the amount of radioactivity released. The second addresses the mechanisms by which the radionuclide releases could result in radiation exposure to people. The third area of study concerns determining the effects of reactor effluent on the quality of Columbia River water. Both the heat and the chemicals added by the effluent are being investigated in the third study area.

Insertion of target materials into a reactor displaces fuel. The remaining fuel must have higher enrichment to maintain reactivity and must operate at higher power density, or higher specific power, to maintain total reactor power. A specific power increase of about 20 percent has been demonstrated power. A specific power increase of about 20 percent has been demonstrated in the U-233 program and in preliminary coproduct irradiations in the N Reactor. Some extension above this is probably feasible with present fuels. However, substantial increase, such as doubling the specific power, may require a change in fuel element design configuration, in fuel core alloy, and in materials used for fuel cladding. In addition, optimum utilization of the N-Reactor recirculating cooling system will require thorough study and perhaps some limited development work. Increasing specific power to improve reactor flexibility with minimum modification of the reactor is especially attractive for the K and N Reactors. It is a possible, though more difficult, alternative to reactor modernization at the small reactors, but it forgoes operating savings and introduces difficult reactor safeguards problems.

This document provides reactor operations daily reports for July 1, 1966 through June 30, 1967.

Plant nutrition was studied as a relation between aerobic respiration and ion uptake in barley. Potassium, chlorine, lithium, sodium, calcium, sulfates, and bicarbonates were studied by root absorption in varying concentrations of carbon dioxide atmospheres. (PSB)

A soil map and a descriptive report of Hanford Area soils grouped according to morphologic and genetic characteristics are presented.

A method for determining numerically local minima of differentiable functions of several variables is described. In the process of locating each minimum, a matrix which characterizes the behavior of the function about the minimum is determined. For a region in which the function depends quadratically on the variables, no more than N iterations are required, where N is the number of variables. By suitable choice of starting values and without modification of the procedure, linear constraints can be imposed upon the variables. 8 figures.

An aerothermodynamic analysis of the SNAP-27 LEM fuel cask is presented for each of three mission aborts. Aerodynamic models for point mass and six degree-of-freedom trajectories are used, and the fuel cask heating rates and temperature responses are predicted for these trajectories. A survey of analytical and experimental studies of separated flow is related to the fuel cask, and a shock tunnel test program is outlined for further fuel cask analyses.

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