The principal types of particle accelerators are described briefly according to operation and history. Known operating particle accelerators are listed with their pertinent dimensions.

"Investigations into the behavior of the gas flow behind spherical or cylindrical blasts have shown that secondary shocks arise within the original detonation gases. The secondary shock, at first weak, is carried outward with the expanding gases. Subsequently it strengthens and bends back toward the origin, arriving there with high intensity. By using some recently developed techniques in shock dynamics a theory is developed by which the motion of the main shock wave, as well as the formation and subsequent motion of the secondary shock, are given by explicit formulae."

"Recent theoretical advances in describing the nucleon-nucleon interaction (particularly in the T=1 state) have emphasized the importance of obtaining an unambiguous experimental determination of the scattering matrix so that the nuclear phase shifts and details of the nuclear potential may be revealed. It is possible to select five experiments, the results of which, in principle at least, determine the scattering matrix and phase shifts uniquely at one energy. Two of these experiments, the cross section and polarization over the angular range of 0 to 90 degrees in the center of mass system, have been made at the University of Rochester at a laboratory energy of about 210 Nev."

Sugar Stock and Sales report for Imperial Sugar Company including a list of sugar sales for the date showing the amounts and estimated balance separated by location, raw sugar, and refined sugar sales.

Introduction: The purpose of this technical report is to review the water chemistry methods and equipment developed for use with the Maritime Loop Irradiation Program conducted in the General Electric Test Reactor (GETR) from December 2, 1960 to July 19, 1962. Special emphasis is given to areas having general application to other high purity water systems. The Appendix includes a discussion of specific conductivity and pH in high purity water systems. A major section of this report is devoted to a review of gross activity levels on coupons of two different surface finishes exposed in the loop coolant system for various time intervals. A major objective of the chemistry program was to select or develop analytical methods such that the analyses could be performed at the loop location by technical personnel who normally operate the loop. By this means, frequent samples were obtained and analyzed directly thus providing close monitoring and control of the loop water chemistry at minimum expense.

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This report addresses the calibration of kerr cell system for high voltage pulse measurements.

A finite element method is presented which utilizes a three dimensional quadrilateral finite element with a stiffness matrix developed in cylindrical coordinated. The method is used to study the behavior of layer cylinders due to asymmetric static thermal loadings. Two types of bonding, rigid and flexible are considered. Additional examples including a pressurized thick walled cylinder and a cylindrical shell under pressure and thermal loadings are presented.

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A half-plant low alum water treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by the analysis of ledge corrosion attack on fuel elements, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in process water treated with two different alum feed rates. Three 20 column fuel discharges, ten from each side of the reactor, have been taken during the test as follows: (1) One discharge prior to the start of the test. (2) One discharge such that the test side was exposed to coolant treated with both high and low alum feed. (3) One discharge under test conditions. This report presents the results from the second discharge under test conditions.

Direct AEC sponsored programs report that: a new mathematical simulation model to handle reactor effluent dispersion was started, final arrangements were concluded for the proposed test of the effectiveness of activated carbon for inorganic ion removal at the Richland Water Plant, the whole body counter used to measure the burdens of radionuclides in Richland school children is being calibrated for persons of small size and with different weight to height ratios; controlled intake of oysters that have accumulated zinc-65 is being used as one phase of this calibration. Assistance to Douglas United Nuclear is reported for missions 1, 10, 11, 13, and 14. Topics discussed here include: diffusion bonding of nickel-aluminium, PCTR experiments, code development, aluminium jacketed uranium fuel elements, and radiochemical analysis of radioarsenic in effluents. The General Electric N-Reactor department reports on:analysis and theoretical interpretation for ice and water, radiometallurgical examination on Al canned targets containing ceramic cores, inspection of irradiated zircaloy-2 clad fuel rods,resonance absorption cross section calculations, and visual inspection of Inconel steam generator tubes. Isochem reports on: dissolution of zircaloy studies, subcritical neutron interaction experiments, carbon monoxide disproportionation on exposure to bismuth oxide, dissolution rates of British alloys in nitric acid, Sr and rare earth …

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A critical analysis of the Al-Ni-U bond and the hot die size bonding technique is given as the result of a literature search. Metallurgical aspects of the bond and the technique of hot die sizing are commented upon in particular.

On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing the men were released to return to work. In compliance with AEC Manual Chapter 0703, an AEC-HAPO committee composed of two AEC employees and five General Electric employees was appointed by the Manger, HOO, with the concurrence of the General Manager, HAPO, to conduct an investigation of the incident. The committee`s purpose was to determine the cause, nature, and extent of the incident, and recommend action to be taken by others to minimize or preclude future incidents of this magnitude. A study of operating practices and operating conditions that appeared to exist prior to, during, and subsequent to the accident was made by the committee. The committee believes that this report provides sufficient information to answer questions which may arise as a result of the criticality incident …

This monthly report details activities of the Battelle Pacific Northwest Laboratory in production and Hanford Plant assistance programs for the month of July 1967.

These specifications, prepared for the N-reactor fuel, provide the framework on which the overall control and guidance of the manufacturing process shall be built.

The current operating conditions at 105-DR, because of the recent Ball 3X drop, dictate temporary lower speed-of-control limits. While is si still not expected that this reactor will be limited by the speed-of- control criterion, it is felt that the limit curves have been temporarily sufficiently reduced as to warrant publication of former limits. Limit curves as a function of weighted graphite temperature for the continuous and block discharge schemes are included in this document. The two sources of the reduction in the speed-of-control limit comes from two sources: (1) While the limit is commonly expressed in MW of pile power level, it is actually a function of maximum tube power, (2) The poisoning effect of the balls lodged in the stack has been estimated at about 15 mk.

The effectiveness and corrosion characteristics of Turco 4512-A, an inhibited phosphoric acid, are being evaluated for N-Reactor primary system carbon steel decontamination by in-reactor decontamination tests, full scale component evaluations, and laboratory corrosion tests. To date these tests have showed that the decontamination procedure is effective for carbon steel decontamination and safe for all primary system materials that will be contacted by the solution. A few materials, namely, 17-4 pH SS, 416 SS, 420 SS, and Easy-Flo 45 braze alloy have not yet been completely tested. Results of their performance will be reported prior to full reactor decontamination.

The fairly recent discovery that tritium is a product of uranium fission prompted the analysis of separations plant waste streams and the local ground water for this radionuclide. The purpose of the sampling and analytical program was to determine the concentrations and relative distribution of tritium in cribbed-waste streams and its concentration and disposition in the local ground water regime. These factors are of interest from the environmental monitoring standpoint; they are also potentially of real value in evaluation of the regional ground water hydrology. This report presents the initial results of the process waste and ground water tritium-sampling program. Two-dimensional comparisons of the ground water tritium analyses with routine gross beta analyses are also presented.