Description of a computer program which optimizes the locations and strengths of magnets for experimental beams at the Brookhaven AGS written for the IBM 7090 computer. Layout, method, and routines are given particular attention, and representative data cards are shown.

"The behavior of charged particles in a plasma-free cusp field, or in a cusp field where there is very little plasma, is studied. The numerical computations described may provide a valid picture of the behavior of particles outside such a body of plasma or in the early stages of creation of such a cusped plasma in the low- beta limit. The computations provide a striking illustration of orbits which neither have constant magnetic moment nor behave so irregularly as to defy explanation."

"Adlam and Allen and Davis, Lust, and Schluter have studied nonlinear plane-waves, propagating normal to the magnetic field, in a cold plasma. One solution of particular interest is a solitary wave, or single pulse. We present a method for solving the analogous problem for a plasma with finite temperature, in the limiting case where the amplitude of the wave is small and where, consequently, the width of the waver is very large."

"This is the third quarterly report on Task II dealing with Methods Development for Radio-Tracing of Coal Product Hydrocarbons With Tritium. The problem of accurate low-level tritium assay for tagged hydrocarbons has been resolved and attention is now primarily directed at the questions of tritium mobility and radio-chemical purity in tagged tracers."

Both in magnetohydrodynamic shocks and in accelerated partially ionized gas flow across a magnetic field, space charge separation occurs that establishes very large electric fields in the direction of motion. The width of the current layers associated with the acceleration is never less than the electron Larmor radius with no collisions and is broadened by electron collisions to a width solely determined by the effective resistivity. The electrons gain an energy regardless of collisions equal to the electric potential difference across the layer. This potential corresponds to the change in kinetic energy of mass motion per ion. For slightly ionized gases, the additional stress of neutral ion collisions within the layer can make the electric potential and hence gain in electron energy very large for only modest changes in mass velocity. Hence ionization may occur when the change in kinetic energy of the ions is small compared to the ionization potential.

Abstract: The acid hydrolysis of [Pt(NH3)3Cl] has been shown to occur to a measurable extent. for this reaction: [APt(NH3)cCl]+ + H2O [chemical equilibrium symbol with rate constant k-1 above and k1 below] [Pt(NH3)c(H2O)]++ + Cl-, the equilibrium quotient was measured at 25 degree C and 35 degree C. At 25 degree C this quotient was 8.4 x 10-5 at [Mu] (ionic strength) = 0 and 25 x 10-5 at [mu] = .318 M. This variation is consistent with the expected changes in activity coefficients. [Delta]H for the reaction was found to be approximately 0. The rate constant, k1 was 2.3 x 10-5 sec.-1 at 25 degree C and it was nearly independent of ionic strength. The acid hydrolysis provides a mechanism for the exchange of the chloride ligand and Cl-. Exchange experiments with Cl36 showed that in addition to the acid hydrolysis, a process, first order in both, [Pt(NH3)3Cl] and Cl- with a rate constant of 6. 10-5 sec.-1M.-1 contributes to the exchange. The behavior of the entire series of chloro-ammines of platinum(II) toward acid hydrolysis and chloride exchange has been summarized, and a likely mechanism for the process has been discussed.

Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.

This is the monthly report for the Hanford Laboratories Operation, April 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

The need for an industrial plant to know its capabilities to rescue personnel and minimize damage to vital operating equipment in the event of a serious accident has long been recognized. Although Hanford`s experience has been without a serious radiation event as characterized in this report, it is prudent to have an objective assessment of the capabilities which do exist and an analysis of the general capabilities which the plant should possess to maximize the effectiveness of rescue action in such an event and to limit the consequences to personnel, vital equipment, and the surrounding environs. It in the purpose of this report to: (1) make an assessment of the capabilities which are currently in place at Hanford to handle the multitude of serious problems arising from a serious radiation event; and (2) define the level of capability which the Hanford Atomic Products Operation should possess to minimize the consequences of such an accident. It is not the intent of this presentation to discuss the possibilities, probabilities, prevention or courses of serious radiation events.

The projection welded brazed closure is being studied as a possible alternate method of closing coextruded Zircaloy-2 clad uranium fuel elements for the NPR. This closure consists essentially of projection welding the Zircaloy-2 cap to the element cladding followed by a fast resistance heating of the cap and exposed uranium face under pressure to braze the cap to the uranium face. The work to date has been entirely on 0.593 inch OD rods and 1.050 inch OD by 0.500 inch ID tubular elements. This closure has the advantage that the entire closure is completed in less than 5 seconds on one machine and consequently the element is at a temperature which would be detrimental to the Zircaloy-2 cladding and uranium bond for a very short time. The amount of uranium removed for this closure is reduced by a factor of 10 over conventional braze closure methods with a substantial savings in uranium and acid milling time. A braze material which is not toxic can be used to bond the cap to the uranium.

The purpose of this report is to present steady state hydraulic demand data for BDF type process assembly with specific enlarged outlet fittings and to compare these data with previous correlations of hydraulic demand for a BDF assembly with standard outlet fittings.

A calculation of the three-group flux distribution of the initial wet critical loading of KW reactor was made using the same calculation techniques as those employed in NPR three-group calculations. The calculation results are directly comparable to experimental data obtained during the KW loading. The calculated radial geometrical buckling of the critical loading is 48.2 {mu}b compared to a measured value of 49.8 {mu}b; these agree within estimated experimental error. The calculated reflector augmentation distance is 54.5 cm compared with a measured value of 49.2 cm. The three-group nuclear constants of the KW lattice components were calculated from 18-group data (APEX-515) based on the flux spectrum of HW-63172. A cell calculation was made to determine the effective constants for the homogenized cell. The calculated k {infinity} of this cell came out 0.998 compared to a measured 1.034. Since the resonance capture of U-238 is difficult to treat, in three-group theory, all error was assumed to be in this parameter which was adjusted accordingly to give k {infinity} = 1.034. The resulting core parameters are given in Table I, along with parameters for the dry, unloaded core and the wet unloaded core.

This report details activities of the Fuels Development Operation for the months of April, May, and June 1961.

The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mixers in the 7th and 15th position from the rear. Fuel cores representing the full range of UT-2 voltage values (grain size converts to d-c voltage) of interest are segregated into three categories: a. Large grains. b. Variations of grain size in an individual core. c. Small grains. Each category will be subdivided into three groups, each covering a small range of values. After canning, the finished fuel elements will be assembled into twenty-seven (27) charges in three latin square patterns for irradiation to a 900 MWD/T exposure goal in D Reactor.

This document presents the total control aspects of the current blanket and central zone E-N loading at H Reactor based on the calculational parameters in Physics of E-N Load compared to Natural Uranium Load at H Reactor, D.I. Monnie, May 11, 1961. The original charge for the E-N core load at H Reactor, (19.37 in. E to 1 in. N) was found to be more reactive than desirable for maximum production efficiency. Therefore a less reactive E to N ratio (18.14 in. E to 1 in. N) has now replaced the original loading.

This is the monthly report for the Hanford Laboratories Operation August 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

Equipment Development is testing a system of operational fueling at 105-KE. This cursory review is made for assurance that the program continues to merit risk of small production loss and development priority. Production Test IP-429-K, which is now circulating for approvals and which provides for up to 150 tubes fitted for operational fueling, is an indication of the immediacy with which, presuming due diligence and barring unforeseen circumstances, the system can be available for production.

This is the monthly report for the Hanford Laboratories Operation October 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

The monthly report for the Hanford Laboratories Operation, June 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

The monthly report for the Hanford Laboratories Operation, May 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

This report discusses benefits in an increase in the flow of water from the lower depths of the Grand Coulee Dam which was used to lower river temperature at HAPO. A net average daily reduction of over 1.2{degree}C resulted at HAPO with a peak of 2.7{degree}C. The Net Production gain from temperature change was 6910 MWD and the Cost of Control was: Grand Coulee Charges $3,120.00, and other (Estimated) 6,880.00 for a total of $10,00.00.

The monthly report for the Hanford Laboratories Operation, November 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and technical administration operation are discussed.

The original charge for the E-N core load at H reactor, consisting of five different types of charges, each group of five containing 199 .947 per cent enriched uranium E-pieces of six inch nominal length and 16 Li-Al I&E (N) pieces of four inch nominal length plus mixers, was intended to provide enough excess reactivity to operate the reactor at all times with reasonable but not excessive flexibility. During actual operation the excess reactivity observed has been somewhat greater than conservatively planned. In addition, a very slight long-term gain rather than the expected loss has been observed up to this time (73 MWD/column average exposure). On this basis, a modification of the original charge makeup has been determined which will permit increased conversion and operating efficiency.

This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.