Abstract: This technical report summarizes all core physics experiments performed on SM-1 Core I and SM-2 Rearranged and Spiked Core I throughout core life. These measurements were obtained on site during the 16.4 MWYR lifetime of SM-1 Core I and 1.6 MWYR lifetime of SM-1 Rearranged and Spiked Core I. SM-1 Core I was the first stainless steel - UO2 dispersion core to burn out in the Army Nuclear Power Program. Experimental techniques are described and a complete history of fuel movements in the core presented. Measurements include control rod bank positions during all core conditions, temperature and pressure coefficients, control rod calibrations, transient poison effects, source multiplication, and stuck rod positions. The effect of core rearrangement and spiking on core reactivity and core life is also reported. Applicable measurements from the SM-1 zero power experiments are included.

From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.

From Abstract: "The electric field is plotted and its construction steps for axial symmetry are given."

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.

The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between January 1 to March 31, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM). The major effort in this period has been devoted to ascertaining and evaluating corrosion behavior of 75 ternary compositions.

This production test is designed to test the feasibility of controlling the amount of air entering a reactor, hence, the burnout of the graphite by monitoring the gas activity. Gas activity comes from the induced activity on argon, which is one of the constituents of air. This production test is basically a test to calibrate the gas activity instruments as a function of various amounts of argon in the reactors gas system. The first two parts of the test are calibration points with different amounts of argon. From these calibration points, extrapolation or interpolation can be used to determine expected activities for other amounts of argon. (GHH)

From abstract: "The divalent metal ions of calcium, magnesium, nickel, and strontium are eluted from a cation exchange column with 1.5M nitric acid and separated from trivalent rare earths, aluminum and yttrium. Prior sequential elution of other metal ions with hydrochloric acid in acetone-water or with dilute hydrofluoric acid does not interfere with the present separation method."

The following report is the third Quarterly Report in a series whose investigative purpose is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure as caused by a combination of absorbed hydrogen and applied stress.

The self-diffusivities of Co60 and Ni63 in cobalt--nickel solid solutions exhibit a greater activation energy below the Curie temperature (T/sub c/) than above. Values of DELTA Q = Q (ferromagnetic) -- Q (paramagnetic) are approximately equal to RT/sub c/. This observation is interpreted to indicate that the increment in activation energy arises from an increase in the formation energy of a vacancy in the ferromagnetic lattice, with the additional binding energy arising from the interaction of a spin with the Weiss field."

"The diffusivities of Fe, Co, and Al in otherwise pure Au were determined by a residual activity technique. It was found that the frequency factors and activation energies of the transition elements into Au are normal relative to the values for Au self-diffusion, and suggest that lattice diffusion is operative, in contrast to the corresponding situation for the diffusion of these elements in Al. This difference in behavior is explained in terms of the marked difference in solid solubilities in the two series."

The objective of this Production Test Supplement is to evaluate at a K Reactor the operational aspects of a proposed method for reducing minimum downtime. The proposed method is to partially override the xenon transient with a block of enrichment in the central region of the reactor. The purpose of performing this test at a K reactor in addition to the original test at one of the older reactors, is to examine the operational aspects unique to a K reactor and to evaluate the feasibility of the method for reducing minimum downtime at a reactor of that type. It is expected that differences in operating techniques will be indicated at the K plant because of its greater size, of different speed of control restrictions and of the variation in the reactivity effectiveness of enrichment, rods, and poisons. The experience at B Reactor with the use of enriched core to reduce minimum downtime indicates the feasibility of proceeding with a similar test at one of the K reactors.

Two methods for measuring target efficiencies are briefly discussed. The second method puts an upper bound on the efficiency and permits observation of instantaneous efficiency, thereby aiding location of losses. Measurements agree well with conventional radiochemical values.

Localized tensile necking and splitting of the Zircaloy-2 clad on coextruded uranium cored fuel elements may represent an ultimate exposure limit. One way to increase the total energy capability of the fuel element is to corrugate the outside cladding so its perimeter is greater than that of a circle circumscribing the equivalent cross-sectional area. Thus swelling of the core will be accommodated by bending of the cladding rather than by large cladding tensile strains. The principal purpose of the irradiation in to demonstrate that fuel with a corrugated outer cladding accommodates more swelling than a fuel with circular outer cladding and, therefore, can be irradiated with the core in the high alpha uranium temperature range to exposures greater than 2000 MWD/T. This document details a proposal that GEH-10-62 be irradiated to a maximum exposure of 3000 MWD/T or to a volume increase of 5 percent as datermined by weight measurements.

From abstract: "The dissociation of acids in tertiary butyl alcohol has been studied by potentiometric, spectrophotometric, and conductimetric methods. Values for the over-all dissociation of perchloric and picric acids and several tetrabutylammonium salts were estimated by the Fuoss-Kraus treatment of conductance data. Potentiometric studies were carried out at constant ionic strength in order to minimize activity coefficient variations. An acidity scale was established from potentiometric measurements at a glass electrode, and conductance values of dissociation constants. A method was developed for the evaluation of the over-all dissociation constant of weak acids using potentiometric data for hydrogen ion activities and conductance data for the corresponding anion activities. Over-all dissociation constants are reported for perchloric acid, picric acid, 2,4-dinitrophenol, and benzoic acid. Apparent dissociation constants from potentiometric measurements at a constant ionic strength were determined for hydrobromic, nitric, hydrochloric, picric, and p-toluenesulfonic acids."

A program has been carried on at Hanford for a number of years to study the effect of neutron radiation on the dimensional changes in graphite. This program has been concerned with the changes measured on small graphite samples which have been exposed to various conditions of temperature and neutron flux. Theoretical studies have also been conducted to determine damage mechanisms. The prime purpose of this research program has been to develop, with the support of the carbon companies a radiation resistant graphite for use as a reactor moderator at high temperatures. In recent years it has been found that graphite contracts under prolonged neutron exposure at temperatures above approximately 300{degrees}C. This contraction is of concern because of the possible effects on reactor operation and life. For example, distortion of process tubes, vertical safety rods, and horizontal control rod channels can cause increased operating and maintenance problems. This report presents information on the actual depression of the graphite moderator at B, D, F, H, DR, and C Reactors.

Iron containing approximately 0.01 wt. % carbon was quenched from 700°C and irradiated in the BNL reactor at 57°C for various lengths of time. The rate of decay of the Snoek internal friction peak was observed at 57°C after irradiation. After a 4-hour irradiation the rate of decay of the peak was one order of magnitude faster than the rate of decay in an unirradiated specimen. Longer irradiation times up to 48 hours caused no further acceleration of the decay rate. This observation implies that in the irradiated specimens there are ten times more precipitation nuclei than in the unirradiated specimens. This is confirmed by electron microscope studies which also show a factor of ten greater concentration of precipitate particles in specimens irradiated for 5 hours at 57°C as compared to an equivalent unirradiated specimen. Electron microscope studies also show that longer irradiation times do not increase further this number of precipitates. Although these experiments clearly demonstrate the enhancement of nucleation by neutron irradiation, it is not known why the incipient nuclei created by irradiation times of longer than 5 hours do not form observable precipitate particles.

The Chase two-dimensional analyzer is a 64 channel by 64 channel analyzer with a magnetic drum memory and a buffered storage system. The memory capacity is 2 counts per channel. The maximum storage rate is limited by the drum speed and is about 800 counts per second for a featureless spectrum.

Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.