Report issued by the Brookhaven National Laboratory discussing data collected from two BNL meteorological towers. As stated in the introduction, "results are presented in graphic form rather than tabular form" (p. 1). This report includes tables, maps, illustrations, and photographs.

In this report we present solutions of the design problem in which a system of quadruple lenses is required to carry a particle beam from given focal lines in the x and y planes to other given focal lines. Particular attention will be given to the case of the anastigmatic lens system which takes a beam from one focal point to another focal point. Since the general problem is almost impossibly complicated a simplification is introduced by breaking the lens system into two parts. The first part of the lens system is required to bring the initial beam to the state where it is parallel to the z axis in both planes. The second part carries the initially parallel beam to the required final condition. Each part will involve two quadrupoles so that the complete system will consist of four quadruples; usually, however, the field gradients in the second and third quadrupoles can be made identical so that those quadrupoles can be combined into one and the system becomes a three quadrupole system. The configuration of the lens element will be as shown in the figures below. These figures indicate also the general character of the beam path in the …

Progress report of the Brookhaven National Laboratory Nuclear Engineering Department providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output from the reactor physics division, the applied chemistry and chemical engineering division, and metallurgy division.

Monthly report from the Reactor Operations Division of the Brookhaven National Laboratory that covers various topics like the different operations conducted, and the amount of energy consumed.

The work of the BNL Waste Processing Development Project has been concerned with developing means to accomplish three main objectives in handling radiochemical wastes. One is to reduce the corrosiveness of the waste. At present some wastes must be stored in SS vessels at high cost, since other tankage would not resist corrosion for any length of time. Hanford has solved a part of this problem by storing a neutralized or alkaline waste which can be contained more cheaply in 1020 steel vessels, although neutralization increases its total volume 50 percent over the original acid solution volume. Another aim in waste disposal is to reduce the mobility of the water. Although equipment is checked and double checked, and corrosion resistance is assured by extra thick-walled vessels, the possibility exists that a leak in such storage tanks may develop. At such times the solution may be carried by ground water into populated areas, whereas a relatively immobile waste would remain a local problem. A third and very important consideration is a desirable reduction in total waste volume. Since costs of waste storage are propositional to the volume stored, any reduction in total volume will reduce the total cost.

We have recently completed measurement of resonance escape probability in the BNL reactor and in several slightly-enriched uranium light water moderated lattices. In addition, WAPD has made available to us data from other slightly enriched uranium-water lattices, so that about 18 lattices in all have been done.

The so-called Fluoride Volatility Processes refer to several proposed non-aqueous methods of processing irradiated fuel elements. In each of these methods, the uranium is fluorinated to uranium hexafluoride and then decontaminated by distillation. One of the methods, involving direct fluorination of the uranium by bromine trifluoride, has been under investigation at BNL since 1950; subsequently a pilot plant was built to study this step of the process. The objectives of the program were to investigate the technical feasibility of continuous dissolution, and to determine the effect of process variables on the capacity of the equipment; namely the effect of temperature, solution composition, flow rate, and uranium history on dissolving time as related to fuel elements of the types used at BNL, ORNL, and Hanford. The nominal capacity of the dissolver was five pounds of uranium per hour and all process equipment was fabricated of Monel. Special equipment components and numerous safety features were utilized. The major equipment development was a canned-rotor pump used for circulation of the dissolver stream through the heat exchanger. A system for continually charging slugs to the pressurized dissolver was also developed. Operation consisted of batch runs which were made with unirradiated BNL slugs in order …

The so-called Fluoride Volatility Processes refer to several proposed non-aqueous methods of processing irradiated fuel elements. In each of these methods, the uranium is fluorinated to UF6 and then decontaminated by distillation. One of those methods, involving the direct fluorination of the uranium by bromine trifluoride (BTF), has been under investigation at BNL since 1950. In 1952, it was demonstrated at BNL that uranium, as UF6, could be satisfactorily decontaminated by distillation in small-scale pilot plant equipment; end in 1953, BNL undertook the job of determining the technical feasibility of a continuous dissolver on a pilot-plant scale. The reason for the project was that the economic superiority of the process seemed to depend upon its amenability to continuous operation.

The cooling of the graphite was started by increasing the fan load and reducing reactor power. This change was accompanied by a temporary increase in exit air temperature, stack activity and some graphite temperatures. Although unexpected at the time, each change can be explained in terms of the change in air flow rate. There were no other unusual conditions noted during the operation. Temperature traverses through the graphite structure in various channels and at various times during the anneal operation are illustrated in the accompanying charts.

It is the purpose of this report to present a quantitative picture of the overall waste problems at the presently operating major A.E.C. sites. Presented herewith are data on the volumes and radioactive concentrations of the wastes handled and effluents discharged, available tankage and processes flow sheets from each site.

The purpose of this new series of reports is to present in roughly finished form the results of the various start-up experiments on the BNL reactor as soon as the analysis of the experimental data is completed.

A new colorimetric method for the determination of cholesterol has been investigated. It makes use of the relatively stable green color given by a purified digitonin precipitate with the anthrone reagent of Dreywood. Equal precision can be obtained with the new method using 1/10 or less of the quantity of material required for present colorimetric methods.

The meteorological control program developed at Brookhaven National Laboratory requires some simple means of classifying atmospheric turbulence so that the dispersion of cooling air from the nuclear reactor may be measured and forecast on a routine basis. The first approach to the problem, was based on the variations of horizontal wind direction as measured by a standard Bendix-Friez Aerovane mounted 355 ft. above ground. The time interval used was one hour. The original system has proven satisfactory in most respects, and is still in daily use.

A number of pipetting aids are commercially available which obviate the necessity of filling pipets by oral suction. Most of the commercially available devices involve fitting the pipet into a soft tight fitting bushing and filling by means of either a piston or a rubber bulb. The pipet is then emptied by means of a valve control which permits, it is claimed, a dispensing accuracy of 0.1mL. It is at once apparent that the probable error (10% for a 1 mL. pipet) is considerably greater than is permissible for great precision. In practice these devices are found to be awkward and after a period of use tend to become even more so due to corrosion of the valve and aging of the rubber bushing and rubber bulbs.

As a result of unreported information, it was suspected by some people that a change in dimension was experienced by 2S Aluminum due to a sudden change in neutron flux impinging on it. This was thought to be of the order of 500 microinches per inch in magnitude. Such an effect, if present, could help explain some of the creep phenomena reported lately (i.e. change in creep rate due to cyclotron bombardment.)

During the last year we have been attempting to increase our understanding of the significance of the various dilution methods used to measure the extra-cellular fluid. When the dilution methods were first proposed to obtain a measure of the extracellular fluid volume, it was hoped that an agent could be found which would distribute uniformly and exclusively throughout this compartment, which would approach equilibrium rapidly, and which could be measured by simple and accurate procedures. We have turned our attention chiefly to the methods themselves using dogs and non-edematous adults as subjects.

This report is a summary of the neutron attenuation data which have been obtained at the Brookhaven shielding facility on a mock-up of the fuel-rod-unloading plug used in the KAPL Reactor. Before this program was initiated, a number of small scale tests had been made in the ORNL lid tank on carbon steel mock-ups of components of the rotating plug. The results of the tests indicated considerable neutron streaming through the vertical steel and air members of the plug. However, the lid tank source strength and dimensions did not permit the tests to be extended to the full plug height. In view of the concern aroused by the ORNL tests and the absence of fundamental information on the transmission of neutrons through steel and the addition height (12') available here resulted in a request for BNL to construct and test a mock-up of a sector of the SIR top plug in accordance with KAPL specifications.

Initial rough measurements of the quality of the gamma radiation from Co-60 in air indicated agreement with the theoretical calculations of Spencer and Fano for an infinite water medium. Further experiments were performed, duplicating the conditions assumed in the calculations. Since the spectral region between 100 kev and 1 mev has already been examined by Hayward, it was decided to investigate in detail the region below 100 kev and above 1.0 mev. Total radiation dosage measurements were made in water using Victoreen ion chambers. The build-up factor was measured as a function of distance. Good agreement was obtained with the results of White. The spectrum below 150 kev was examined with a small NaI(Tl) scintillation counter and both the shape of the spectrum and the attenuation as a function of distance was in good agreement with the calculations. At distance less than 30 cm from the source the spectral shape changed, gradually broadening with the peak shifting to higher energies. The primary region above 1.0 mev was examined using a large NaI(Tl) crystal, and the gradual loss of resolution in the two primaries as a function of distance with an increase in lower energy events was shown. The measurements to …

This report is the culmination of a year of progress and planning in the high-energy particle field. During this year the Brookhaven Cosmotron has been successfully completed and brought into operation for research at 2.3 Bev. Preliminary experimental results with the copious output of π-mesons are in process of publication. Multiple production of mesons has been observed, a few V-particles detected, and the interactions of π-mesons in hydrogen have been studied. Yet it already appears that higher energies will be needed to produce and study the several new heavy particles detected in cosmic ray observations.

A number of questions have arisen in regard to the interpretation of personnel monitoring results reported to users of the Brookhaven neutron monitoring service. The original announcement was rather brief and did not contain most of the technical characteristics upon which an evaluation of results must be based. The following paragraphs have been composed with the hope that they will clarify the meaning of the exposure reports.

In recent months, experiments investigating the total, non-elastic, transport, etc., cross-sections of U-238 have been performed. It is the purpose of this memo to examine these data and to obtain from them information which will be of use in refinements pile calculations. In cases, e.g. transport cross-sections, where experimental data do not suffice, the theory developed pertaining to the continuum model of the nucleus has been depended upon. One of the fundamental requirements of this model is that the spacings of the energy levels in the compound nucleus are small compared to their widths and that consequently many levels are excited by the incoming particles. As a result there are many more modes of decay and the continuum model is an average over these levels.

The method of spherical harmonic tensors developed Mark for solving the Boltzmann transport equation in isotropic media is herein extended to anisotropic media for cylindrical geometry. A formal solution is given for the case of two concentric cylindrical media, A and B, but no numerical work has yet been done. The following treatment differs from a similar one by the H. K. Ferguson Co. in that the external medium B is assumed to be both a neutron absorber and finite in extent rather than a non-absorber and infinite in extent.

This memorandum clarifies the present status of ξ measurements in the uranium-water lattices.

The following report concerns the application of a relaxation mesh method for the determination of the average flux within the moderator of a light water moderated, 1.027 per cent U-235, hexagonal lattice with a volume ratio (V_H2O + V_Al)/V_Uranium of 4:1. It was hoped that the calculation would enable one to determine any differences in flux which might result from the fact that the unit cell is a hexagon instead of a cylinder. Because we were primarily interested in the effect due to geometry we applied the same theory, diffusion theory, to the hexagon by means of the mesh method and to the equivalent cylinder.