Diffusion theory and transport theory approaches to the problem of a nuclear reactor with a transverse air gap are compared. It is suggested that the differences in results for thin gaps is due to the fact that diffusion theory does not adequately represent the flux distribution in the immediate vicinity of the gap. For mathematical conveniences previous treatments of the gap problem have made use of fictitious image piles which exaggerate the neutron losses. The extent of the error is estimated by direct neutron leakage calculations.

Preliminary data are enclosed in Tables I, II, II, IV, V, and VI. Tables I to V are data for round nickel tubes in a vertical and inclined (45°) position. Table VI contains some preliminary data for nickel rectangular channels (0.060" and 0.050" spacings) in a vertical position.

The rapid development of the field of atomic energy during the past few years now permits the exploration of applications to medicine involving new concepts in the treatment of cancer. One such has been the study of neutron capture therapy which is being developed at the Brookhaven National Laboratory.

As a result of an operating nuclear reactor, several accelerators and many laboratories using radioactive isotopes, considerable amounts of radioactive gaseous, liquid and solid wastes are generated at Brookhaven.

One might expect that the Cosmotron would offer certain advantages over cosmic rays for the study of heavy unstable particles; provided, of course, that it can produce them. In the first place, the conditions under which they are produced could be controlled to a considerably greater extent. In the second place, it might be possible to arrange conditions under which they would be observed more abundantly, an actual beam of heavy mesons being the ideal situation.

The study of the interaction of the electromagnetic field with nuclei has proved very fruitful for the elucidation of many details of nuclear structure. The γ-ray transitions observed in either absorption or emission can be divided into three classes, depending on whether the matrix elements of the transition are (1) much larger, (2) approximately equal or (3) much smaller than those expected for single proton transitions which are usually taken as a norm. In class (1) we find (a) the broad transitions leading to the "giant resonances" in the nuclear photo-electric effect, and (b) the "fast" transitions between low lying states, especially for even-even nuclei far removed from magic numbers. The large matrix elements and the regular dependence of their magnitude on the atomic weight speak for cooperative phenomena in which many nucleons or the nuclei as a whole are involved. In class (2) we find the much studied M4 transitions which give strong support for the single particle model; they have rather uniform matrix elements. Some finer points remain to be understood, especially why some odd nuclei do not show the expected ratio for |M|^2 of ~ 2:1. The transitions belonging to class (3) require further selection rules and …

The absorption bands induced in α-Al2O3 by gamma and reactor irradiation have been studied. The slight coloration due to γ-rays saturates. Bands specific to reactor irradiation have been found and their growth studied.

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.)

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 …

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.

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.

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.

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.

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.

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.

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 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 …

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 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.