Drag coefficients were determined for various irregular objects such as glass fragments, stones, steel fragments, and spheres by means of drop tests for use in a mathematical model to correlate nuclear explosion blast experiments. Drop tests were also made on small laboratory animals and extrapolated to estimate the drag properties of man. A method was developed to estimate the average drag properties of man from his total surface area. (D.L.C.)

Report issued by the APDA over studies conducted on the Doppler Effect in fast neutron reactors. Methods and results of the studies are presented and discussed. This report includes tables, and illustrations.

The authors have previously reported that deuterium oxide in the drinking water of either male or female mice produces sterility. An investigation of some of the conditions--with particular reference to time--of deuterium oxide treatment to produce sterile C{sub 57} male mice indicated that the sensitive phase of sperm production centered around the late prophase of meiosis. In some experiments, although D{sub 2}O was almost completely absent during maturation of the sperm, and when the mice mated, these sperm exhibited the effects of their much earlier contact with D{sub 2}O. No viable offspring were obtained from these matings. They concluded that the presence of D{sub 2}O during the late prophase and meiotic divisions interfered with the normal construction or division (or both) of genetic material. It was suggested that changes in the forces, principally hydrogen bonds, in macromolecules affected their structural characteristics and resulted in abnormal division. The objective of the experiments reported here was to determine the phases of embryonic development of the mouse at which the lethal action of deuterium oxide on sperm is manifested. These investigations on embryonic growth initiated by sperm developed in D{sub 2}O have yielded additional evidence that D{sub 2}O severely damages the genetic material …

Angular distribution and kinetic-energy spectra of fragments, and cross sections for fission of gold with 68- to 124-Mev C{sup 12} ions have been obtained by observation of the fragments in two types of detectors, gas scintillation chambers and silicon p-n junctions. From the parameters used to fit the angular distributions to the theoretical curves of Halpern and Strutinski, we have obtained the average excitation energy of the fissioning nucleus at the time of fission. This quantity is approximately 25 Mev, which is nearly independent of bombarding energy, suggesting that fission is preceded by the emission of several particles from the compound nucleus. The fission cross section increases from a value of 100 mb at 68 Mev to 1.28 b. at 124 Mev. Over this range of bombarding energies, the total fragment kinetic-energy release rises from 142 {+-} 6 to 146 {+-} 6 Mev. At all bombarding energies, the variation of laboratory-system kinetic energy of the fragments with laboratory-system angle indicates full momentum transfer by the bombarding particle to the fissioning system.

Quarterly report describing progress on a project to develop and evaluate high-temperature tungsten alloys. This report discusses properties for specific base alloys at room temperature and under high temperatures.

From foreword: This report presents the results of a study on the stability of phosphors under high energy beta radiation.

From introduction: This report sets forth the results of a study of canned-motor and controlled-leakage pumps for large pressurized water reactor nuclear plants.

To permit the irradiation of one dummy fuel element assembly for one operating period and to permit, during a subsequent operating period, the irradiation of one defected, four-rod-cluster UO{sub 2} fuel element assembly, in a KE front-to-rear test hole. The fuel material is natural UO{sub 2} of 95 per cent theoretical density; the cladding is zircaloy. The defect in the assembly is artificial and will be made before irradiation by drilling a .005in. diameter hole through the cladding near the mid-point of two of the rods.

Failure of reactor rear face connectors is a problem at the reactors. The vibration has been studied at H and F Reactors to assist in the development of a permanent replacement for these connectors. Vibration data were otained from rear nozzles, connectors, and crossheaders within the process tube pattern for the following operating conditions: full cold water flow prior to reactor startup, normal operating power level, and during transition from shutdown to normal operating power level. The vibration patterns at 105-F and 105-H were similar in magnitude. Oscillograph data are presented.

This report documents analysis of radionuclides from reactor effluent water samples. Separation from the sample matrix is accomplished by successive carbonate, hydroxide and fluoride precipitations. Experimental data is provided.

The cap-spire pulsing technique of preheating the cap-spire portion of the fuel assembly does significantly improve the brazing of the cap-spire assembly. The air pocket at the spire wafer junction is fully removed. The cap side wafer is essentially 100% wetted with brazing alloy. Destructive tests show that a 4 to 1 improvement in most quality measurements is achieved over present cap preheating techniques, without using additional cleaning step of spire etching. The pulsing is accomplished by a cammed drive system, using a stroke of three-fourths of an inch with a spring return. The system is driven by an electrical gear reduction motor at a rate of 1.4 pulses per second. A preheating cycle of 21 {plus_minus} 2 seconds is used for the current I&E cap designs. The cap-spire assembly does not require any special treatment other than the normal chemical cleaning.

Goal exposure and power level planning and administration on either a short-term or long-term basis, is heavily dependent upon assessment of the level of metal performance. It is the purpose of this document to present a method of monitoring the metal performance level employing the concept of control charts, and to propose adoption of this method as the basis for detecting changes in the metal performance level of the three main types of production fuel elements, i.e., C-II-N, O-II-N, and K-III-N material. Supplemented with predetermined decision rules for evaluating the extent to which the metal performance level has improved or declined, these control charts become valuable tools for use in making IPD operating decisions.

Ex-reactor high temperature, high pressure recirculating water loop defect-tests have been made on SPR size coextruded fuel tubes. The behavior in terms of fuel corrosion loss and fuel shape distortion for ``pin-hole`` type defects has been determined. Effects of annular spacing on the defect-test behavior and the influence on the mechanical and metallurgical conditions of adjacent components has been observed.

Enclosed is the data that was collected during the recent thermal cycle of KER-1. This data includes the RTD readings and information taken from the thermocouple fuel element. In conjunction with obtaining data on film build-up, the test provided an excellent opportunity to study the effect of temperature on measured tube power. It has been noticed that the KER reactor tubes appear to produce more power (greater {Delta}T) at lower operating temperatures, but the reason for this power increase is not known. With the additional thermocouples to measure water temperatures at the center of the tube, it should be possible to determine if this increase is from the graphite or from the fuel elements.

Changes in operation and corresponding changes in the reactivity status of Hanford reactors are the result of a continuing effort to improve operating efficiency. Trends data related to these changes in operation and reactivity have been published previously for the periods from 1950 through 1958. The purpose of this report is to include trends data for 1959. All included data were selected from the sources listed as references on page 48. Bar graphs in the first part of the report show yearly averages of selected data, and tables in the last part of the report show maximum, average, and minimum values. This document presents trends data for C, H, KE, and KW reactors while a second document, HW-64931, presents trends data for B, D, DR, and F reactors. Data included in past years which have not been included in this report are trends in pile power level at shutdown omitted due to a security status change regarding power levels. Potential non-equilibrium gains and potential equilibrium gains,data were added in this report. Notice that all reactivity values are listed in the unit per cent excess k.

This monthly document details activities of the Hanford Operations Office during the month of June 1960. (FI)

None

The objective of the production test detailed in this report is to evaluate Zr-5 w/o Be brazed end closures on enriched tube-and-tube elements irradiated in high temperature coolant in the KER Loops.

This monthly document details activities of the Hanford Operations Office during the month of May 1960. (FI)

The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.

From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.

None

Abstract: This memorandum presents the possible applications and instructions for using REDCROSS, an IBM-704 computer program.

Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.