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 present studies are concerned with the distribution of sodium and with the kinetics of its exchange among the various compartments of the sodium space in nephrotic children.

The biological effect of absorbed unstable isotopes is related, in some cases, to the chemical changes resulting from radioactive decay rather than to the accompanying radiations. The special geometric and metabolic characteristics of bacterial cultures are employed to show that genetic effects of P32 may be attributable to the rupture of the phosphate band in deoxyribose nucleic acid. Other examples to illustrate the use of the nuclear disintegration technique an an indicator of the specific chemical changes which can produce biological and genetic effects. Possible evolutionary significances are discussed.

A method for measuring the thickness of unprocessed nuclear emulations based on X-ray absorption is described and discussed

With the advent of super atomic bombs, radioactive fallout has become a major concern in connection with civil defense. There has been great interest in the degree to which various surfaces may become contaminated and in the possibility of decontamination of much surface after the fallout has occurred. The surfaces of interest are, of course, those commonly used for buildings, roads, sidewalks, etc. Since weapons tests provide radioactive fallout similar to that which would be encountered as a result of atomic warfare, such fallout should be an ideal source of contamination for the testing of surface characteristics. While this might be true close to the test location where actual mechanical fall-out of dry material can be studied, it should be borne in mind that conditions at locations well away from the area of the bomb explosion will be different in several respects. Fallout will come mostly as a result of precipitation since particle size will be relatively small and the rate of disposition of dry material will be slow. Despite the limitations, the fall-out from weapons tests is a readily available source of contamination for testing the characteristics of surfaces and some useful results should be possible.

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.

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 biological evaluation of the thermal neutron capture reaction of boron-10, B10 (n,α)Li7 + 2.786 MeV, has previously been studied, using different particles from the boron-10 thermal neutron capture reaction compared with 250 kvp x-rays has been reported as 1.05 for spleen-thymic weight reduction (1), as 1.5 to 2.0 for skin lesions in pigs (2), and 1.87 for skin lesions of the rabbit's ear (3). The significance of such a calculation is felt to be unreliable for the boron-10 reaction in animals because of the vagaries of dose determination resulting from irregular boron distribution, and by the presence of an adventitious irradiation from fast neutrons and capture gammas that is inadequately determined at present. Our present experiment attempts to circumvent the difficulties attendent to studies of the boron-10 reaction in animals by comparing the effect of this reaction on the proliferative capacity of HeLa cells with those produced with 250 kvp x-ray.

In these lectures we will discuss some examples of information about magnetic properties of solids which can be obtained by neutron scattering. We consider a scattering process in which a neutron with wave vector k and spin σ is incident upon a solid in state q>. (Here q stands for all of the quantum numbers which describe the state of the solid, such as spin and orbital electronic states, phonon numbers, etc.) After interacting with the solid, the neutron goes off with wave-vector k' and spin σ', leaving the solid in state q'>. In performing an experiment of this sort one does not usually observe the initial and final spin states of the neutron or the initial and final states of the solid. We must then sum over all possible final states and average over all initial states.

The driving force for liquid metal corrosion is the equilization of chemical potential for dissolution of all solid surfaces in contact with the liquid. In any practical system, this is an impossible goal; therefore, one observes several mass transfer processes.

This paper is a review of the presently available experimental information about the K-meson decay interaction. The charge dependance of the interaction is not discussed since this has been treated in another paper at this conference. Most of the information derives from the three body decays, but there is one piece of information which can be obtained from the two body decays.

TbMn2 crystallizers with the cubic Laves-phase structure which may be regarded as the spinel structure without the anions. The "A" sites are occupied by Tb ions and the "B" sites by Mn ions. Neutron diffraction powder patterns run at 4.2°K exhibit a number of extra reflections characteristic of a modulated magnetic structure. These additional reflections can be indexed on the basis of a spiral modification propaganda along with a wavelength of 50.3 Å. The spiral axis is along. The "B" sites are ordered in a manner which is entirely analogous to the low-temperature ordering of Fe3O4: the two sublattice spirals being 180° out of phase. The A sublattice is in phase with a particular one of the two B sublattices. The combination of the internally compensated B sites and the ferromagnetically coupled A sites leads to a ferrimagnetic spiral.

We consider the kinetic isotope effect in three center reactions of the type of A+BC→AB+C. Such model calculations are a good approximation to primary hydrogen isotope effects. For abstraction or transfer reactions, B becomes H, D, or T. The dynamics of the three storm system are calculated for a general quadratic potential, with the assumption that the potential energy is constant along the reaction coordinate (flat top barrier). This model system can be calculated in detail and serves to illustrate the relationship between kinetic isotope effect and chemical bonding in the transition state. The statistical mechanical part of the calculation can be carried out exactly within the framework transition state theory or in any one of a number of approximations. The γ bar method gives particularly good insight into the chemistry of the problem with a minimum of arithmetic.

The discussion during the summer study centered on objectives and techniques of experimentation at high center-of-mass energies using either colliding beams or super-energy accelerators Also a great deal of interest was expressed in possible increase in intensity of existing and proposed accelerators. This raised attendant questions about space-charge limits, intensity-dependent beam instabilities and residual radioactivity. Papers on these other associated topics will be found in the proceedings.

Optical absorption and photoconductivity measurements have been made on single crystals of pure synthetic rutile (TiO2). Reactor irradiations at 70°C totaling 4.8 x 10 18 nvt fast and 1.69 x10 19 nvt slow did not produce any discernible optical absorption bands; however, the transmission decreased 5 percent at all wavelengths. Reactor irradiation induced a [illegible] five photoconduction peaks in the wavelength range 4200 to 14,000 A. In addition the photopeak at 4065 A (3.05 eV) was enhanced and there were drastic changes in the dependence of photocurrent with light intensity. Gamma-ray irradiations as large as 10 9 r do not change the conduction properties. The photocurrent is proportional to a power of the light intensity; the power range from 0.65 to 1.24, for the crystals described in this work. The photocurrent vs. voltage dependence is more complex.

The plastic behavior of both unirradiated and gamma-ray irradiated NaCl single crystals has been studied with a variety of techniques. These include the determination of stress-strain curves, and photoelastic, surface, topography, and F-center absorption band, measurements, The different stages of deformation in unirradiated crystals are compared with the corresponding stages of irradiated ones. One effect is that irradiation greatly extends the easy glide region. Some insight into this behavior is obtained from the photoelastic and topography measurements. In unirradiated crystals almost all glide occurs on one slip system and there is considerable pile up. In irradiated crystals slip occurs on two perpendicular systems, the number of operating glide planes is, at least, doubled, and the pile up is very much reduced. Both the yield-point and F-center concentration increases rapidly with dose up to approximately 10 7 r and at a much slower rate for larger doses. Also investigated was the effect of crystal shape (or geometry) on the stress strain curves obtained from unirradiated crystals. The most interesting results are, the yield-point decreases with increasing cross section and that the slope of the linear strain hardening region depends on the radio of the crystals shortest dimension to its height.

The present core of the Brookhaven Graphite Reactor consists of some 4900 highly enriched uranium fuel loaded in 615 horizontal fuel channels passing through a 25 foot cube of graphite moderator and reflector. The core is divided into two halves (north and south) by an 8 cm. wide vertical gap in the center of the graphite. The cooling air enters the reactor through inlet filters, at the rate of 270,000 CFM, passes into the central gap and flows bi-directionally through the north and south halves of the core. It then enters the collecting plenums and flows into the north and south ducts. The air is first monitored by the north and south exit air monitors located within the pile building. These are moving filter tape monitors with beta scintillation detectors. They are essentially operational monitors and are maintained by reactor operations. They are essentially operational monitors and are maintained by a reactor operations. The air then passes through the exit air filters, heat exchanger, venturi and on to the fan house where the north and south ducts join. After the fan house the air is monitored by Argon-41 by a Kanne ion chamber syste.

Boron-10 has a high thermal neutron capture cross section (3880 barns). Following neutron capture, the subsequent nuclear disintegration produces an alpha particle and a lithium-7 nucleus with the release of an average of 2.34 MeV for the particle irradiation, and in 93% of the reactions there is also the emission of an 0.48 MeV gamma ray: [equation not transcribed]. The kinetic energy is divided between the lithium-7 nucleus and the alpha particle giving the equal and opposite momentums with a range in tissue of about 8-14μ or approximately 1 cell diameter (1). This fact and the reported favorable partition of boron between tumor and the normal brain suggested a possible therapeutic usefulness which has been investigated clinically. The object of our study is to document the biological effects of the B10 (n,α) Li7 reaction on the brain of dogs injected with boron-10 30 minutes prior to irradiation with thermal neutrons. For this, we felt it desirable to estimate a dose for the boron-10 reaction which if exceeded, produces destruction of normal tissue. This dose could then be a reference dose to be utilized as a maximal limit for the irradiation of normal tissue. We have assured that the largest fluence …

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.