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Abstract for the Glasgow Meeting - "International Conference on Nuclear Physics": Gamma Transitions and the Shell Model
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 are more difficult to describe in general terms. Among the better understood "slow" transitions are some electric transitions which have a reduced transition probability either because they correspond to neutron jumps, or because they involve more than one particle in the transitions.
Accelerator Development Department Internal Report
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 two planes.
Accident in Continuous-Dissolver Pilot Plant of Fluoride Volatility Project on May 15, 1957
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.
Accuracy of Relaxation Length Measurements
We consider here the accuracy of relaxation lengths measured during the water-uranium lattice experiments. Since such an analysis for all measurements would take a great deal of time, we have applied it to just one lattice. This one (2:1 water-to-metal ratio) was chosen completely at random.
Additional Experiments on Stored Energy in BNL Reactor Graphite
In the memorandum entitled "Stored Energy in BNL Reactor Graphite", dated February 25, 1953, there is described an experiment conducted by Gurinsky's group to determine the energy per gram of irradiated graphite released in a 200°C anneal. Similar experiments were subsequently conducted by W. Kosiba, differing from the original in two particulars: a) Instead of two graphite samples, one normal, and one irradiated, Kosiba used only an irradiated sample which he heated first to release the stored energy, and then again after the energy was released. In this way, he obtained time against temperature curves for both normal and irradiated graphite from the same sample. (These curves are graphed for each run in Figs. 1 thru 5.) b) The vycor tubing used in the original experiment was not used by Kosiba. Five runs of this experiment were selected, Runs 4P, 13, 36, and 40 at furnace temperatures of 200°C, and Run 45 at a furnace temperature of 400°C.
Analysis of Meteorological Tower Data, April 1950 - March 1952, Brookhaven National Laboratory
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.
The Approximation with Anisotropic Effects for Cylindrical Geometry
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.
Area Survey Manual
Report issued by the Brookhaven National Laboratory discussing the area survey manual covering the 15 service stations. Design and operations of the service stations are presented. This report includes tables, illustrations, photographs, and a map.
The Area Survey Manual of Brookhaven National Laboratory: Area Radiation Detection Instrumentation, Maintenance, and Results
Report issued by the Brookhaven National Laboratory discussing the instrumentation, operation, and maintenance of the established area radiation monitoring stations. This report includes maps, tables, illustrations, and photographs.
Boiling Burnout Newsletter No.1
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.
Brookhaven National Laboratory Annual Report: 1954
Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1954. As stated in the introduction, "the progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory" (p. v).
Brookhaven National Laboratory Annual Report: 1956
Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1956. As stated in the introduction, "the progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.
Brookhaven National Laboratory Annual Report: 1957
Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1957. As stated in the introduction, "the progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.
Brookhaven National Laboratory Annual Report: 1958
Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1958. As stated in the introduction, "the progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.
The Brookhaven National Laboratory Emergency Radiological Monitoring Team
Report issued by the Brookhaven National Laboratory discussing the Emergency Radiological Monitoring Team. Equipment, training, and personnel required for the team is presented. This report includes tables, illustrations, and photographs.
Calculation of Average Flux in Moderator of Water Lattices by Means of a Relaxation Method
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.
Calculation of Transport Cross-Sections of Uranium
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.
Capture - Positron Ratios for Allowed and First-Forbidden Transitions
Report issued by the Brookhaven National Laboratory discussing capture positron ratios. As stated on page 1, "the purpose of this report is to present aids for the simple determination of the relative probabilities of K-electron capture and positron emission for allowed and first-forbidden transitions" (p. 1). This report includes tables, and illustrations.
Classified Progress Report of the Reactor Science and Engineering Department; April 1 - June 30, 1950
Technical report outlining the progress of reactor completion and startup events by the Reactor Theory, Physics, Radioisotope Development, Geology, Meteorology, Waste Concentration, and Waste Disposal groups in the Reactor Science and Engineering Department of Brookhaven National Laboratory.
Classified Progress Report of the Reactor Science and Engineering Department for the Year 1949
Technical report covering classified activities of the Department of Reactor Science and Engineering since its inception in January, 1949. This if focused on the research, evaluation, and redesign of the reactor as well as the tests on various reactor components and engineering design to correct structural defects as they have become evident through reactor use.
Classified Progress Report of the Reactor Science and Engineering Department January 1 - March 31, 1950
Technical report indicating the progress made in the first quarter of 1950 only for the classified projects in the Reactor Science and Engineering Department, including continuous processing breeder blanket studies, sub-critical experiments, and metallurgical experiments like fluid fuels, materials testing, reactor reconstruction, and reactor component testing and service.
Color Centers Induced in Al2O3 by Reactor and Gamma-ray Irradiation
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.
The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia
Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Conference on Waste Processing; Meeting of the U.S. Atomic Energy Commission Waste Processing Committee March 27-28, 1950; Section 1. Brookhaven National Laboratory Waste Problems
Technical report summarizing the waste problems of the Brookhaven National Laboratory site and the integration of projects constituting the need for intensive and extended research into the development of processes, equipment, and systems to dispose of this nuclear waste. This report also outlines the first session for the March 27-28, 1950 meeting of the Committee at Brookhaven National Laboratory.
Conference on Waste Processing; Meeting of the U.S. Atomic Energy Commission Waste Processing Committee, March 27- 28, 1950; Section 2. Evaporation
Technical report summarizing the waste problems of the Brookhaven National Laboratory site and solutions to problems of nuclear waste evaporation; outline of the second session for the March 27-28, 1950 meeting of the U.S. Atomic Energy Commission Waste Processing Committee at Brookhaven National Laboratory.
A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures
Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
The Cosmotron Radio Frequency Accelerating System
The proton beam in the Cosmotron is accelerated to an energy of 2.3 billion electron volts by a radio frequency voltage which is impressed across an insulated gap in the ferrite loaded accelerating cavity of the vacuum chamber. To maintain a constant orbit radius as the beam is accelerated, the frequency of the accelerating voltage must increase from the initial value of 370 kc/sec to 4200 kc/sec during the one second magnet pulse. Over the entire 11:1 frequency range, a minimum gap voltage of 2000 volts rms must be maintained. At every instant throughout the magnet pulse, the frequency of this voltage must be a predetermined function of the magnet field to a high degree of accuracy. Frequency errors greater than about .2 percent result in loss of beam due to excessive radius changes. Smaller errors than this however, can excite fatal phase oscillations in the beam if they occur rapidly. As little as .005 percent frequency modulation can result in total beam loss if it occurs at a rate of several kc/sec, where the beam is most sensitive to such disturbances.
Design Study for a 15-BeV Accelerator
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.
Determination of Cholesterol Digitonide with Anthrone
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.
Diffraction Studies of Possible Ordering in α-brass
Recently, there has been some evidence to point to possible ordering in the α-brasses. Masumoto et al. have concluded from their specific heat measurements that there is a possibility of ordering in the α-brasses. In particular they observed an anomaly in the specific heat curves for the α-brasses for the temperature range from 200 to 260°C and explained these results upon the basis of a change in local or short range order in α-brasses at these temperatures. In connection with the study of radiation damage effects in α-brass ordering has been suspected. Rosenblatt has annealed 70-30 α-brass previously annealed at 350°C and cooled to room temperature at 190°C for six weeks. He observed a decrease of .90 ± .03% in the electrical resistivity of α-brass measured at -196°C after the anneal at 190°C.
The Effects of Chorio-allantoic Transplants of Adult Chicken Tissues on Homologous Tissues of the Host Embryo
Selective incorporation of radioactivity from proteins of labeled chorio-allantoic grafts of adult chicken tissues into proteins of homologous tissues of host chick embryos.
Effects of Gamma Irradiation on Nitro Alkane Formation in the Purex and Redox Systems
A study of the effects of gamma radiation with respect to the formation of nitro-hydrocarbons on the Purex and Redox systems shows that no appreciable formation of nitro-paraffins occurs.
Evaluation of Carbagel Process for Air Refrigeration for Use With BNL Reactor
Technical report outlining the use of the Carbagel process in nuclear reactors, its technical feasibility, and case studies of the Carbagel process and its theoretical and technical use for reactors such as the Brookhaven National Laboratory reactor.
An Experimental and Theoretical Study of the Subcritical BNL Reactor
Technical report outlining the theoretical study of the sub-critical BNL (Brookhaven National Laboratory) reactor, and a comparison of reactor performance with the purpose of presenting the experimental results of the experimental methods. Presents experimental results and and a detailed discussion of the experimental methods along with theoretical analysis and evaluation of the results.
The Experimental Application of Neutron Capture Therapy to Glioblastoma Multiforme
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.
Final Report on Reactor Fuel Element Research, Development, and Production
Technical report describing the Brookhaven National Laboratory nuclear reactor and the physical studies of heat transfer and efficiency conducted to improve nuclear reactor operations.
Gamma Ray Polymerization of Acrylamide in the Solid State
The polymerization of vinyl monomers can be initiated by heat, ultraviolet radiation, and various catalysts. More recently, ionizing radiation has been shown to effectively initiate vinyl polymerization. However, polymerization in the solid state by ionizing radiation is not reported in the literature, although several papers have been published that describe briefly the thermal polymerization of divinyldiphenyl, Leuch's anhydride and in greater detail the peroxide catalyzed polymerization of acetaldehyde. The purpose of this note is to describe some experiments which demonstrate that crystalline acrylamide undergoes polymerization upon irradiation with γ-rays from an intense Co-60 source. Below its melting point the monomer shows little or no tendency to polymerize thermally.
Irradiation Effects on 2S Aluminum
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.)
Liquid Reactor Fuels: Bismuth-Uranium System
Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.
LMFR-9 Static Corrosion Behavior of Materials in Bismuth and Uranium-Bismuth Solution at 550°C
Report issued by the Brookhaven National Laboratory discussing corrosion behaviors of materials in bismuth. As stated in the introduction, "this report will present the details of the corrosion testing and the results obtained to date on materials tested under static conditions in bismuth media" (p. 1). This report includes tables, illustrations, and photographs.
LMFR Progress Letter for April 1954
Summary of miscellaneous updates related to the project. This includes information on the following. Simplified equations for modeling reactor conditions. Solubility tests involving thorium, bismuth, and protactinium. various other measurements and tests involving thorium, uranium, protactinium, bismuth, aluminum, and various other salts.
LMFR Progress Letter for February 1954
In a third run with the fluorine torch, the settling chamber wells were kept hotter than before (≥ 625°C); the flame was cooled by diluting the fluorine with helium. In the analysis of the products, 99% of the thorium fluoride fed in was accounted for, but only 64% of the protactinium activity. Part of this was carried in the exhaust gases past the cold trap and into the soda line disposal column, where it was detected by survey meters. The stripping of protactinium from the solid was somewhat more efficient than before; 77% of the feed which was recovered from the settling chamber had lost 72% of its original specific activity. About 15% of the input activity was trapped on the cold fingers with very little thorium fluoride.
LMFR Progress Letter for March 1954
Summary of miscellaneous updates related to the project. This includes information on the following: the declassification of a relevant paper, solubility measurements, static corrosion tests, various other tests involving bismuth, magnesium, uranium, protactinium, and thorium.
ξ Measurements
This memorandum clarifies the present status of ξ measurements in the uranium-water lattices.
Measurements of Water Lattices
A series of measurements of ε in slightly enriched uranium, light water lattices is presently under way at Brookhaven. Figure 1 shows ε as a function of water-to-metal ratio for .600" diameter rods, of 1.3% enrichment. Because of interaction between neighboring groups of rods, ε increases rapidly as the water-to-metal ratio decreases.
Memorandum
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.
Microclimatology at Brookhaven
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.
Neutron Capture Gamma Ray Spectra
A series of measurements was performed to investigate the gamma ray spectra, in the region from about 100 kev to about 3 Mev, resulting from the capture of thermal neutrons in a number of elements. The purpose of the experiment was to supplement the high energy capture gamma ray data in order to remove some of the ambiguities from the proposed energy level schemes and to obtain information for the Shielding Group of Brookhaven National Laboratory on elements normally found in reactors.
Neutron Streaming Through Boundaries in a Mock-Up of the SIR Rotating Plug
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.
The Ninth and Tenth Annealing of the Graphite Moderator Structure in the BNL Reactor
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.
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