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.)

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 …

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.

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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.

The rupture model presently being used by IPD Research and Engineering is the Weibull cumulative distribution function which in the region of interest, the model can be expressed approximately as: F(X) = failure rate in number of ruptures per total number of tubes, P = average tube power, T = average tube outlet temperature, M = exposure a{sub o}, a{sub 1}, a{sub 2}, a{sub 3} = parameters determined from rupture experience. F(X) = a{sub o}P{sup a1}T{sup a2}M{sub a3}. The parameters a{sub 1} = 3.3, a{sub 2} = 8.7, and a{sub 3} = 5 were estimated from experience with solid slug side-other and side-hot spot failures occurring from the spring of 1956 to the end of 1957, and were found to hold quite well for experience through 1958 as well. The model using the aforementioned estimates of the a{sub 1}, a{sub 2} and a{sub 3} parameters is being used in numerous ways, including fuel performance measurement (estimating values of a{sub o}, in essence), reactor optimization, project justification, production scheduling and forecasting, and fuel element test design. From time to time, doubt has been expressed about the appropriateness of applying these estimates of the a{sub 1}, a{sub 2} and a{sub 3} parameters, …

The purpose of this report is to provide scope and justification for the installation of one new 900 HP pump in the 181-D Building and to tie the two 36-inch headers together in order to supply sufficient water to increase production at 105-D and 105-DR.

The engineering considerations are given on which the design and construction of tanks for the storage of low-level radioactive waste solutions were based. The tanks have a nominal capacity of 1,300,000 gal each. While conforming to the principle of total confinement, these tanks were built at a considerably lower cost than the tarks designed for storing high-level radioactive wastes. This saving was brought abeut by the elimination of a number of features such as cooling coils and the angular space and secondary saucer container around the tank. (auth)

The 9 single-crystal elastic moduli pertaining to principal crystallographic axes of alpha U at 25 deg C were determined from measurements of high-frequency wave velocities for 21 modes in seven single-crystal specimens, using the phase-comparison method of McSkimin. From the results the elastic compliances, compressibilities, and Poisson"s ratios were computed for the principal axes. Th variations with crystal direction of the stiffness moduli, Young's moduli, and rigidity moduli were plotted. The nature of the anisotropy for the different moduli indicated that the nearest neighbor interatomic bonds are considerably stiffer than the next nearest bonds, which are only slightly larger in interatomic distance. (auth)

A micrometer that utilizes eddy current techniques is described. The gage is capable of measuring nominal 0.5000-in. aluminum rods to an accuracy of plus or minus 0.00005 in., and is unaffected by residual nonconductive surface filins such as oxides or corrosion products. (auth)

Sodium-24, produced by the Al (n, alpha )Na/sup 24/ reaction, has been found in the coolant of reactors using aluminum-clad fuel elements. Methods of calculating the activity due to scdium-24 are outlined. This activity was calculated to be normally 1.4 x 10/sup 5/ to 6 x 10/sup 5/ disintegrations per min per ml. The Na/sup 24/ isotope disintegrates with 2.76- snd 1.38-Mev gammas. (B. O. G.)

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As part of an earlier program of investigation in this laboratory, studies were made of the gamma ray spectrum and the beta ray spectrum of cerium-144. In the present work, seme coincidence studies were made on one of the beta groups appearing in the cerium-144 decay and on the gamma rays appearing in the deexcitations from the energy levels of praseodymium-144. Sources of cerium-144 were prepared frcm carrier free radioactive cerium-144 as supplied by the Oak Ridge National Laboratory. The sample material was more than two years old at the time of preparation of sources. No additional chemical purification was attempted. Sources for use in the beta crystal spectrometer were mounted on thin Formvar film on spectrometer ring mounts. The gamma ray spectrum of cerium-144 in the energy range 20 kev to 180 kev is shown in Figure 1. This spectrum was determined using a 2-inch by 2-inch NaI(Tl) crystal. The pulse spectrum was analyzed by a Radiation Instrument Development Laboratory (RIDL) 200 channel analyzer. The spectrum gives clear evidence of gamma ray peaks at 34 {+-} 3 kev and 134 {+-} 2 kev. A rather broad peak at 80 kev is observed. An indication of a gamma ray group …

The SNAP I development program was initiated to develop a 500-watt turboelectric power conversion system for space applications, Superheated mercury vapor was used as the heat conversion working fluid. The conversion system was to obtain thermal energy from the decay of a radioisotope fuel such as Ce/sup 144/ . Each of the major components and systems is summarized with respect to initial design objectives, development progress to the point of program termination, results obtained from tests and, where indicated, future growth potential. Reference is made to 10 other reports which describe, in detail, the major components of this power generating system. Also included is a bibliography of documented reports that are related to the power conversion system design criteria or system integration into a flight vehicle. (auth)

No conclusions could be made concerning tbe distribution of hydrogen injected into the reactor coolant because the samples were taken only from the purification loop through which tae hydrogen was added. No comparison of the uniformity of distribution obtained by injecting hydrogen through either the AC or the BD purification loop could be made. Comparative data were not taken until 9 days had elapsed since injecting hydrogen and the concentration was near tbe lower limit (15 cc/kg). The rates of hydrogen loss durirg the test were 5.9 cc/ kg/day for hydrogen injected through the AC purification loop, and 4.1 cc/kg/day for hydrogen injected through the BD purification loop. (auth)

The Blue Print File groups provided by HAPO for Lurochemic were attached to cover pages, which listed the BPF number and the information contained. These cover pages were combined and an ORNL-CF number assigned. (M.C.G.)

Capital investments and the cost of power were estimated for 21 heavy- water-moderated, natural-uraniumfueled power-reactor plants, ranging in capacity from 100 to 460 Mw(e). Comparisons were made of hot- and coldmoderator reactors and of the relative merits of pressuretube and pressure-vessel designs. Reactors cooled with liquid D/sub 2/O, boiling D/sub 2/O, /sub 2/O steam, and helium were evalunted. A cold-moderator pressure-tube reactor cooled with boiling D/sub 2/O shows the most economic promise of the D/sub 2/Omoderated reactor systems studied to date. Reactors of this type have sufficient reactivity to permit satisfactory fuel exposures, but the development of additional technology is a prerequisite for optimum designs. At capacities of 300 and 400 Mw(e), the estimated power costs from the current designs of boiling-D/sub 2/O pressure-tabe reactor plants are 11.3 and 9.8 mills/kwh, respectively. From liquid-D/sub 2/-cooled concepts of comparable capacities the indicated power costs are 7 to 20% higher. With an active development program, a power cost of 8.0 to 8.5 mills/kwh may be attained in a 300 Mw(e) boiling-D/sub 2/O reactor plant within the next decade. (auth)

Experimental determinations of the longitudinal dispersion coefficient and the Peclet number were made for three binary gas systems. The experimental technique involved measuring the dispersion of a step function input to a column packed with glass beads. The diffusional model was employed to obtain the differential equation describing longitudinal dispersion in a packed column. This equation was solved with suitable boundary conditions, and the solution was used in the analysis of the experimental dispersion data. The experimental results show a variation in the Peclet number from 0.1 to 0.6, and in the eddy dispersion coefficient from 0.03 to 1.0 cm/sup 2//sec for the Reynolds number range from 0.03 to 1.0. (auth)

Comparison data were needed concerning stainless steel plate and sheet for use as linings in shielded cells. An investigation was made to obtain information concerning surface finish specifications, prices, and decontamination properties of 1/4-in. thick plate with a No. 1 finish, 3/16-inthick sheet with a No. 1 finish, and 11 gauge sheet with a 2B finish. The ASTM specifications relating to stainless steel sheet and plate describes the procedures used to obtain the various finishes but does not give specific tolerances for the surface finishes. The finishes may vary considerably depending upon production conditions. (auth)