Report containing information regarding He4 vapor pressure measurement as of 1958, the recent history of the vapor pressure temperature scale, and a series of tables containing these measurements.

This report addresses the analysis of a rocketdyne report on rockets.

The purpose of this document is to present the Title I scope design which will constitute the basis for Title II detail design of the Plutonium Reclamation Facility.

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To observe and document the extent and location of crud deposits and corrosion or any other defect in components of the Reactor Coolant System and its auxiliaries. This particular performance involves a ruptured bellows of the 1C reactor coolant pump D/P cell.

By means of high temperature X-ray techniques the crystal structure of lanthanum, cerium, praseodymium, neodymium, ytterbium, and possibly gadolinium was found to be body-centered cubic at temperatures near their respective melting points. For ytterbium a hexagonal close-packed structure was also observed, which was shown to be stabilized by atmospheric impurities. Evidence for possible high temperature crystalline transformations in gadolinium, terbium, dysprosium, holmium, and lutetium was obtained by means of electrical resistance measurements; erbium gave no such evidence. X-ray data were used to derive empirical equations which describe thermal expansions coefficients of scandium, yttrium and the rare-earth metals. Europium exhibits a rapidly decreasing coefficient of expansion with increasing temperature, which may be a consequence of a gradual promotion of one of the 4f electrons into the conduction band. The hexagonal rare-earth metals were found to have nearly the same axial ratio at their respective transformation temperatures.

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.

Inertial pressure of the KEWB (Reactor Safety Experiments) is calculated assuming that the inertial pressure rise is attributable to fission-nucleated bubbles. (C.J.G.)

A new rear nozzle has been developed by Mechanical Development (A), IPD to alleviate the stuck gun barrel problem on the process tubes at F reactor. This nozzle is called the 105-F rear face floating nozzle (RFFN) and is shown in Figure 4. The purpose of this study was to determine the hydraulic operating characteristics of this nozzle and to compare these characteristics with those of the standard nozzle assemblies. This report is essentially an addendum to EW-63756 1 which presented energy loss data for various outlet fitting assemblies for possible use on the BDF type reactors The experimental data for this study were obtained with the use of the hydraulics mockup in the 189-D Thermal Hydraulics Laboratory.

Activities in a study to determine the differential pressure across the EGCR core following a pipe rupture in of quick-opening valves in bypass lines around the reactor are evaluated, and recommendations concerning these valves and other components are included. (J.R.D.)

Measurements were undertaken to compare the performance of a hydrogen- palladium diffusion coil to a palladium resistance wire assembly in measuring hydrogen concentration and to obtain data to evaluate a Swartout Palladium Resistance Gage electronic readout unit. No comparison could be made since the instruments were never in satisfactory service at the same time. The data taken with each instrument are compared with data determined by laboratory analysis. A review of the data indicated that the units were unreliable. (B.O.G.)

The mapping function, the complex potential, and the equations for the streamlines and equipotential lines for the fluid motion through a spout were obtained. One nudiscussed. (auth)

Radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown were determined. Radiation levels in the 1AC, 1BC boiler chamber enclosures and in the reactor chamber enclosure were on the average higher than in previous tests. The highest reading obtained was 7.5 mr/ hr and the lowest reading was 0.03 mr/hr; the mean level was 3.76 mr/hr as compared to 1.37 mr/hr in previous tests. (W.L.H.)

An investigation was conducted to obtain measurements of radiation levels inside the hemispherical heads of the 1-B heat exchanger. The radiation levels were measured at the handholes on two occasions with an interval of 640 hrs between them. A very large increase was noted and could be explained only by the possibility that the measurement survey points were not identical. (J.R.D.)

The radiation level and its decay were measured at expected hot-spots in the reactor container, 1AC and 1BD boiler containers, and pressurizer cubicle after plant shutdown for refueling. Initial measurements indicated rela tively high radiation levels in certain areas. Maximum initial readings were 500 mr/hr, 400 mr/hr, 530 mr/hr, and 195 mr/hr in the reactor container, 1AC boiler container, 1BD boiler container, and purification cubicle, respectively. (W.L.H.)

An investigation was conducted to determine the adequacy of storage capacity and operating procedures of the waste disposal system during reactor cooldown for refueling. It was found that the waste storage capacity and the operating procedures were adequate. (J.R.D.)

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The results of a study are presented which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for, a reactor producing perturbed neutron fluxes exceeding 10/sup 15/ thermal neutrons per square centimeter per second and 1.5 x 10/sup 15/ epithermal neutrons per square centimeter per second. To accommodate the experimental samples, the reactor fuel core is four feet long in the direction of experimental loops. The vertical arrangement of reactor and experiments permits the use of straight and vertical loops penetrating the top cap of the reactor vessel. The design offers a high degree of accessibility of the exterior portions of the experiments and offers very convenient handling and discharge of experiments. Since the loops are to be integrated into the reactor design and the in-pile portions installed before reactor startup, it is felt that many of the problems encountered in MTR and ETR experience will cease to exist. Installation of the loops prior to startup will have an added advantage …

Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).

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.

A study and tests of the feasibility and best method of reaming rear face Parker fittings has been made. Flow increase of 8 percent, based on maintaining the same front header pressure, can be obtained at B, D, and F reactors by reaming the rear Parker fittings to .610 inch and using existing rear face hardware. Tests indicate mechanical strength will not be significantly reduced, high frequency vibration will not be increased, and that methods of reaming are available.

Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO/sub 3/ solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO/sub 3/. Plutonium and uranium values in washed precipitates can be recovered by successive treatment of solid residues with caustic and nitric acid. Removal of nitric acid from uranium-molybdenum alloy dissolver solutions by boil-down procedures and by reaction with formaldehyde is discussed. Solutions obtained after removal of nitric acid constitute satisfactory low-acid Redox process feedstocks. (auth)

This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory work. (JT)

Abstract. An IBM-650 computer code for the detailed unfolding of [gamma]-ray spectra obtained from NaI scintillation counters has been developed. The procedure is set up to remove analyzer scale dependence and to largely remove energy dependences. Computer time is about 1 minute per [gamma]-ray.