Abstract: "The purpose of this investigation is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 have been hydrogenated to 200 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture has been observed which can be attributed to the delayed failure phenomenon; it appears that these materials are relatively insensitive to static fatigue. The effects of grain size, temperature, cold deformation, and superheated water and steam corrosion on susceptibility to delayed failure are being determined."

Technical report describing how to estimate the energy deposition efficiency of the kinetic energy of recoiling fragments from nuclear fission in a chemically reacting system. Since it is not always possible to directly measure the deposition the report describes how to estimate through the aid of fission fragment range data.

Technical report describing "A means for automatically determining the coordinates of a point at the center of a bubble chamber track." from the abstract.

Technical report describing a bubble chamber film track measuring stage designed for maximum versatility that was build at Brookhaven National Laboratory. The report includes photographs and diagrams of the device.

Report describes a few experiments designed to test the analysis of some systems where chemical energy can be converted to electric energy. From Abstract: "If a chemocouple is defined as an isothermal closed circuit, composed of two or more homogeneous ionic aqueous phases separated by two or more barriers of different sets of ionic transport numbers, we find that a spontaneous electric current flows in the closed circuit."

The report objective is to establish the amino acid composition of sperm whale myoglobin. From Summary: "The homoprotein that comprises 96% by weight of the protein present in crystalline sperm whale myoglobin may be received into at least five components by chromatography on the carboxylic resin IRC-50."

This report discusses the alternating gradient synchrotron at Brookhaven National Laboratory and provides a preliminary discussion on experiences to date and experiments in progress.

Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.

Technical report outlining the effects of chromosomal abnormalities in tetraploid Argentine flint maize pollination, and subsequent generations.

"Test results indicated that graphite is not suitable for seal face material. A program to evaluate various materials and seal face geometries was initiated. A seal run using nucerite-bearium combination was carried on for six hours."

The ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for 1 to 26 energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane.

A comparison of methods of capital cost estimation used for nuclear fuel reprocessing plants shows that, because of the special nature and complexity of such plants, cost estimation methods for conventional chemical plants involving the use of cost factors are not applicable and will give low estimates. Cost factors which are available from other countries where reprocessing plants are installed should be used with caution since those factors apply only for the particular design philosophy used and pertain to industrial conditions which are different in this county. Capital cost estimation methods involving direct take-offs from detailed design drawings are necessary to obtain reliable estimates. The methods of estimating operating costs for nuclear reprocessing and conventional chemical plants are similar.

A method is given for constructing the complete neutron spectrum for a well-moderated thermal reactor such a HIFAR, from the total effective flux, the temperature of the Maxwellian, the epithermal spectral index and the total integrated fission flux. A sample calculation is also included.

Abstract: In the March-April 1962 shutdown of SM-1 Core II, the SM-28 element will be re-inserted in SM-1 Core II and an SM-1 Core I element will be removed. An SM-1 Core II europium absorber will be replaced by a Ag-Cd-In absorber, and surveillance specimens will be inserted above the core support structure. Analysis of these changes concludes that re-insertion of the SM-2B stationary element and insertion of surveillance specimens do not affect hazards potential previously defined for SM-1. Replacement of the europium absorber by the Ag-Cd-In absorber will have negligible effect on reactivity control worth of the rod. The absorber meat section is encapsulated to prevent exposure of silver alloy to the primary coolant; postulated release of silver due to a cladding defect, after 2 years irradiation in SM-1, would not cause a hazard such as to restrict access to the vapor container. Possibility of steam formation in the air gap between the absorber core and cladding, causing a cladding failure, is remote. Deformation of the absorber section sufficient to cause the rod to stick, would not impair the ability of the other rods to shut down the reactor safely.

Abstract: This preliminary technical report covers design of the SM Type 3 element, its use .in.. SM-1 Core III, and planned use in the Type 3 Core for PM-2A. The Type:3 element characteristics are compared with Type 1 (SM-1 Core I) element nuclear, metallurgical, thermal and hydraulic characteristics and fabrication. The effect of using the Type 3 element in SM-1 Core III and. its planned use in a Type 3 Core for PM-2A is discussed with regard to operation, shielding, reactor safety and all conceivable special problems.

Abstract: This technical report summarizes the results of research and development tasks performed during Phase I of this contract and presents recommendations for future development work. Work is reported in the areas of plant assembly and relocation, housings and footings, waste heat dissipation, instrumentation, refueling systems, waste disposal, shielding, core nuclear thermal and hydraulic studies, gaseous waste processing (BWR), and critical experiments on a 5 x 5 array of Type 3 fuel elements.

Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are described along with the radiation measurements made in these areas.

Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel mockups are presented. The uncertainties associated with the measurements are also given. In addition to graphical and tabular presentations of the test results, discussions are provided on the experimental techniques and theory. A review of the analytical models is provided in addition to the calculational results. A special analytical study of the the PM-2A Core I power distribution and absolute power level determination is given. A comparison of the experimental and analytical results is made and conclusions and recommendations presented.

Abstract: This report presents metallurgical .analyses and corrosion tests conducted to determine :causes of failure of two SM- 1 reactor vessel studs due to fracture in the threaded areas, after 23 months' operation (March 1959). Conclusions of corrosion tests are: (1) failure of the studs was caused by stress corrosion cracking, (2) contributing factors to failure of the studs were improper control of heat treatment of the studs and absence of treatment for stress relief after thread grinding operation.

Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of experimental data. Physical characteristics determined include distribution of fuel and B-10 in the fuel plates, minimum critical mass, control rod bank calibration, and integral rod worth. The report concludes with an analysis of the experimental data including estimated uniform and non-uniform burnup rates.

From abstract: "Iron(III) can be separated from many elements by extraction from 6 to ͟8M hydrochloric acid. The extraction is carried out by passing the aqueous hydrochloric acid solution through a column packed with 2-octanone adsorbed onto a poly-fluorocarbon resin. Fluoride, phosphate, sulfate or citrate cause no interference. Traces if iron(III) can be separated quantitatively from large amounts of copper(II) or zinc(II); traces of titanium(IV) can be separated from large amounts of iron(III)."

From abstract: "The hydrides of group VB an VB elements, except CH4 and NH3, have been prepared and, except for PbH4 and BiH3, their mass spectra studied. Fragmentation patterns and appearance potentials of the positive ions from these hydrides are reported. The ions have been tested for excess kinetic energy and this energy was found to be negligible. The average M-H bond energies and the ΔHf° obtained from appearance potential data agree well with values obtained by other methods. Evidence is cited for the existence of distibine."

From abstract: "A study has been made of the yields of gaseous products labeled with C11 from the C12(γ, n) reaction in liquid cyclohexane. The effects of variations in the radiation dose and in the concentration of dissolved iodine during irradiation on the yields of these products were studied in order to elucidate the reaction mechanisms. A reaction model was developed as a method of assessing the relative importance of radical and molecular processes. The data suggest (1) that the formation of C11 labeled CH4, C2H4 + C2H6, and C3H6 involves a hot radical process while (2) the formation of C2H2 is by a molecular reaction with cyclohexane."

From abstract: "The first order correction in αZ to the Bethe-Maximon pair production cross section is calculated for the case where the incident photon and one of the electrons has an energy much greater than mc2. Comparison of these calculations to the experimental data of Plimpton and Hammer shows an improvement ina greement between theory and experiment of approximately a factor of 1+(αZ4π/15) for low positron kinetic energies. However, for positron kinetic energies of the order of 1 Mev no improvement is obtained."