Progress report on programs in target research and in accelerator research.

A study was conducted on the elution behavior of curium (III), americium (III), plutonium (III), actinium (III), plutonium (IV), neptunium (IV), uranium (IV), thorium (IV), neptunium (V), plutonium (VI), uranium (VI), lanthanum (III), cerium (III), europium (III), ytterbium (III), ytterium (III), strontium (II), barium (II), radium (II), cesium (I) with 3.2 M, 6.2 M, and 12.2 M HCI solutions from Dower-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. In order to explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5g-ortibals in the actinide elements.

Quarterly summary report of studies conducted through the Radiation Laboratory, University of California. Some results reported in the report may be of a preliminary or incomplete nature.

The document provides reports on medical and health physics, particularly on the biological studies of radiation effects, the metabolic properties of various materials, radiation chemistry, health chemistry, and health physics.

The fission and spallation reactions caused in uranium by bombardment with high energy protons (340 to 350 Mev) were investigated. The reaction products were separated from the target by chemical processes and identified by their radioactive properties. The relative yields of the observed fission products were measured, and the results plotted as a function of mass number. Several of the spallation products were identified and their yields estimated.

Abstract: Since the viscosity-temperature relationships of fluorocarbons are somewhat unusual, when compared to hydrocarbons, for example, it was decided to measure the viscosities, at several temperatures, of various fluorolube oils. The calculation of the viscosity of a blend of oils is at best an uncertain operation, varying considerably with the method used. A comparison of various methods was indicated, in order that reasonably accurate values might be assumed for theoretical composites. The densities were measured at corresponding temperatures for use in converting viscosities, and for their value, per se.

Measurements were taken to provide experimental evidence for determining the feasibility of a proposed method for converting Pu240 to 241 by exposing shielded plutonium to selectively transmitted pile neutrons.

The remodeling, fabrication, and instrumentation of a high vacuum system are described. The faults encountered with the old system and their solution are outlined. Tests were made on diffusion pump oils and on the reduction of pump oil back diffusion. The measurement of high vacuum pressures by a cold cathode ionization gage at various points on a vacuum system are discussed.

This report refutes earlier calculations made in the flux level of exponential piles. The results of the earlier calculations made on subcritical assemblies using critical assembly equations are in error. The calculations used in this report were more successful.

Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.

Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.

Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and training program outline.

Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and a training program outline.

From abstract: "Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the lactates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the light-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trihydrate was prepared only by the addition of alcohol to a sirupy solution. Since it was not as deliquescent as the lactates of lanthanum, cerium, and praseodymium, some of its properties could be studied. The lactates of all the other rare earths, samarium through lutetium, as well as the lactate of yttrium, separated readily from aqueous media as trihydrates--the solubility of the hydrated lactate decreasing as the atomic number of the rare earth increased. Thermal decomposition of the crystalline lactates, except those of neodymium and samarium, proceeded through dihydrated and anhydrous states to a composition corresponding roughly to LnlacCO3 at a temperature of about 290-300°C. Ln2(CO3)3 or Ln2O(Co3)2 were observed. In order to make a comparison, thermal decomposition of the rare-earth glycolates was studied also. Solubilities in water at both 20 and 60°C have been tabulated."

From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with the models proposed."

Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shut down, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The general arrangement of the heat exchanger described in this report presents a conventional design utilizing known materials and existing methods of fabrication. In further consideration of all concepts, designs and analyses developed during this period of the program, it is felt that this preliminary design will provide an intermediate sodium heat exchanger of lower cost …

In view of the increasing number of methods for determining plutonium in terms of weight rather than radioactivity, a need has arisen for a plutonium compound that can be used as a gravimetric standard. An easily prepared compound that dissolves readily in nitric acid is desirable. The present study was made to determine the feasibility of using plutonium triflouride as a plutonium standard. The preparation, composition, stability, and ignition of the compound are discuss, as are certain properties of the plutonium dioxide resulting from ignition of the trifluoride.

The magnetic field of the AGS ring can contain particles of magnetic rigidity about 34 Bv/c. This includes not only protons of kinetic energy 33 Bev, but also 32 Bev deuterons, 64 Bev alpha particles, and conceivably heavier nuclei such as 188 Bev carbon nuclei. It will be shown in this paper that such nuclei can be injected and accelerated in the AGS if some rather small modifications are made in the injection and acceleration systems. What physics could be done with such beams? Several types of experiments may be suggested. In the first place, since the deuteron is a rather loosely bound combination of a neutron and a proton, it is likely to break up when it hits a target nucleus (stripping reaction). In a considerable fraction of the collisions the neutron will go straight on with essentially unchanged energy (half the deuteron energy). Therefore, with an internal target bombarded by 30 Bev deuterons one should obtain an intense, rather well collimated and monochromatic beam of 15 Bev neutrons in the forward direction.

This technical report describes the digital computer codes used for the aerothermodynamic calculations that were involved in evaluating the Tory II-A reactor.

This report is an outgrowth of the MURA Users' Conference of June 1959. At that conference the group on beam separators discussed the problem of whether particle separation could be achieved at the machine energies under consideration. A preliminary version of the scheme outlined here was given at the conference. Later, after flaws were discovered, it was modified. The attempt is not to show that this is the way it should be done, but to show with reasonable certainty that there is at least one way it can be done.

An exact treatment of the structure of tracks in nuclear research emulsion recently was attempted with some success. Many of the proofs also appear to be generally valid for bubble tracks in Wilson chambers. This is a summary of the results that are applicable to tracks of charged particles in bubble chambers.

This quarterly progress report describes the ongoing research at the Metallurgy Division at the Oak Ridge National Laboratory. In particular, this report discusses the thorium research program, the slug problem, the preferred orientation and anisotropy in metals, fundamental studies of alloying, and the ANP program.

Internal-conversion coefficients may be thought of as consisting of two parts: a usually dominant part which depends only on the atomic number and the nuclear transition energy, and a usually small part depending explicitly on nuclear transition matrix elements. This latter part arises from the penetration of the converting atomic electrons within the transforming nucleus.

A previous report on this subject (Brookhaven National Laboratory, AGS Internal Report, ECR-4) described in detail the methods of measuring the injected and accelerated proton currents in the Brookhaven AGS up to May 1961. At that time the accelerated current was measured by extracting the bunch frequency component of the signal given by a pair of radial position observation electrodes. The injected current was also determined by the signal induced on a similar pair of radial position electrodes. Absolute values were then determined from machine parameters and a wire measurement of the electrode sensitivities. Linac currents, however, were measured with transformers, calibrated by putting known current pulses through a single turn loop. As described in ECR-4, a crude current transformer was placed on the AGS ring and cross-calibration measurements were carried out using a half turn injected beam. The pickup electrode value was then found to be about 10% higher than that given by the current transformer. This amount of disagreement was within the estimated accuracy of the measurements and calibrations used at that time.