Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)

Discussion is given on the welding fabrication of tungsten, molybdenum, niobium, and tantalum. Properties which make the four refractory metals important are tabulatcd along with titanium which is given for comparison. Extensive evaluation was conducted using the gas, tungsten arc welding process employing both manual and machine welding. Design data were obtained exclusively from machine welded sheet materials. Flash welding, resistance spot welding and brazing, electron beam welding, and high frequency resistance welding processes were also applied to molybdenum alloys. The oxidation of molybdenum, tantalum, and niobium in flowing air at 2000 deg F is also given. (P.C.H.)

This report is about the congressional priviledge, because of which people could be immune to liabilities for Slander and Libel.

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A total of 455 mlce, rats, gulnea plgs, and rabbits was subjected to lmpact at velocitles ranglng between 25 ft/sec and 51 ft/sec. The deslred velocities were generated by allowlng the anlmals to free-fall from various helghts to a flat concrete pad. The ventral surface of each anlmal was the area of impact. Problt analyses of the 24-hr mortallty data ylelded LD/sub 50/ lmpact veloclties with 95% confldence limits as follows: mouse, 39.4 (37.4 to 42.0) ft/ sec; rat, ft/sec; and rabbit, 31.7 (30.2 to 33.3) ft/sec. The LD/sub 50/ figures for the mouse and rat were slgnificantly higher, statlstically, than those for the gulnea plg and rabblt. The small spread ln the LD/sub 50/ values suggested little variation ln the tolerance of blologlcal systems to impact. Further, the steepness of the mortallty curves lndicated a narrow survlval range to lmpact. Extrapolatlon of the experimental data to the 70 kg anlmal yielded a predicted LD/ sub 50/ impact velocity of 26 ft/sec (18 mph). Literature relevant to the human case was revlewed and the tentative appllcabllity of the predlcted flgures to adult man ls discussed. (auth)

Revisions in the reactor system and operating procedures necessary for carrying out a proposed dry critical experiment in the EBR-II are described. The safety aspect of the program is considered. The critical experiment will be conducted in the EBR-II prior to filling the primary system with sodium. The facility, experimental program, operational and experimental procedures, and hazards and plant safety are described. (M.C.G.)

Recent work on isotopic x ray sources is reportcd. The research was directed toward optimization of high-level isotopic sources and evaluation of their use in typical scientific and technical applications. The resulting experi- mental data are used in obtaining an approximate mathematical formulation of x- ray output as a function of beta energy, target mnaterial, and source configuration. (J.R.D.)

Activitiee are described in an investigation to develop refractory U materiala for superior reactor fuels. Uranium carbide was prepared by cold pressing in pellets with densitier of 92 to 96% of theoretical. Uranium nitride was synthesized, and it was found that dense specimens (95% of theoretical) could be obtained in N-deficient powder, however in stochiometric compositions the maximum density obtained was 85% of theoretical. In other work dense uranium silicide was prepared and several properties of UC, UN, and U/sub 3/Si/sub 2/ were studied. (J.R.D.)

Tables of the energy, pressure, and chemical composition for a stellar mixture, originally a pure Fe/sup 56/, are presented as functions of temperature and density. They cover a range of conditions pertinent to the evolution of supernovae, involving the deconiposition of iron into helium plus neutrons, and the later stage of decomposition of helium into neutrons and protons. Relativistic degeneracy of electrons is included in these calculations. (auth)

A test was made to obtain a record of radiation contamination levels during core I seed 1 refueling operations. The recorded survey data indicated generally lower radiation levels than had been expected. (J.R.D.)

Two groups of plutonium bars, one group containing 165 ppm iron and the other 678 ppm iron were end-quenched from the beta, gamma, delta, delta-prime, and epsilon phases. In general, cooling rate was found to have three striking effects on microstructure. The alpha grain size was found to decrease with increasing cooling rate during cooling from all phases. Upon cooling high-iron plutonium from the epsilon phase, the size of the Pu--Pu6/sub 6/Fe eutectic network decreased with increasing cooling rate. Cooling high-iron plutonium from temperatures between 413 and 460 deg C produced a wide variety of Pu --Pu/sub 6/ Fe configurations in the microstructure. Finally, the size of an unidentified spheroidal inclusion, soluble in the delta and higher temperature phases, decreased as cooling rate increased across the delta to gamma transformation. These effects of cooling rate can be used to indicate the cooling rate or thermal history that a particular plutonium specimen has encountered. A linear relationship between the alpha grain size and the Pu--Pu/sub 6/Fe eutectic network size was observed. The network size was roughly two times larger than the alpha grain size. Hardness traverses on each of the bars indlcated no apparent effect of coollng rate during quenchlng on …

An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development eIforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, ldaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes. Bulk densities of 0.8 g/cc were increased to 2.9 g/cc by selective use of fluxes and cold compacting techniques. This means that power densities of up to.001 w/cc will …

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Abstract: "The objectives of this program are the development of zirconium-base alloys possessing exceptionally good corrosion resistance to 680 F water or 750-900 F system and/or improved strength at elevated temperatures. Approximately 100 binary compositions were prepared and screened by corrosion testing in 680 F water; selected compositions were exposed to 750 F steam. The data obtained indicate promising bases for ternary and quaternary alloys. Related investigations involving zirconium purity and heat treatment for improvement of corrosion properties are proceeding. Hydrogen pickup and mechanical properties will be used as acceptability tests on promising compositions."

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotropy of the beta-rhombohedral structure has been observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 degrees to 2050 degrees). No metallographic evidence of a three-phase reaction of dilute alloys is observed.

This document reports progress during the month of February, 1961, recording investigations and studies of a flow rate using a curved pipe or S-tube and documenting measurements of mass flow, tube design and construction.

Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1960 and was conducted by the United States and the European Atomic Energy Community (EURATOM).

This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.

A block-loading of striped columns and tubes simulating a blanket loading were analyzed for product (Pu, tritium, E-metal) after irradiation in IP-255-A-9-FP. Results are rationalized to full-pile values; pile conversion ratios and pile gains are given.

The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mixers in the 7th and 15th position from the rear. Fuel cores representing the full range of UT-2 voltage values (grain size converts to d-c voltage) of interest are segregated into three categories: a. Large grains. b. Variations of grain size in an individual core. c. Small grains. Each category will be subdivided into three groups, each covering a small range of values. After canning, the finished fuel elements will be assembled into twenty-seven (27) charges in three latin square patterns for irradiation to a 900 MWD/T exposure goal in D Reactor.

Wetting of the aluminum components by aluminum-silicon brazing alloy is a major factor influencing the quality of the fuel elements. Several process variables associated with the impact extrusion of aluminum components influence the resulting Al surface. In addition, these processing variables interact with the HAPO component production cleaning process to give varying results. Purpose of this document is to define the parameters for selecting, preparing) testing and evaluating the AlSi wetting potential of aluminum components used in the lead-dip process, and to provide a tool for measuring the acceptability of aluminum components for the preparation of fuel elements.

During the 0800--1600 shift on July 7, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 3 and Loop 4 instruments indicating a possible fuel element failure in Loop 1. The KE Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant samples and a thermocouple wire sample taken from Loop 1.