This report contains seven different configurations of support blocks.

Before a reactor is launched into a satellite orbit about the Earth, the hazards to the population must necessarily be considered in the event that the reactor re-enters the Earth' s atmosphere and possibly impacts with the ground. Analytical and experimental efforts for calculating these potential hazards as they apply to SNAP-2 and -10A are described. (auth)

The analytical results reported herein are a description of the nuclear environment produced by the Aerospace System Test Reactor at General Dynamics/Ft. Worth in the LRP Mechanical Radiation Test No. 901.

Progress in health physics is reported under 20 topics. Separate abstracts were prepared for 19 topics. Education, training, and consultation are also discussed (M.C.G.)

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Three silicone-based conductive adhesives were formulated and evaluated. One of the formulations had a resistivity of 0.089 ohm-centimeter after aging one week. After the same period the other two formulations had resistivities of 0.871 and 38.0 ohm-centimeters, Erratic adsorptive behavior of / sup 140/Ba was traced to in impurity in the Ba--/sup 140/La stock solution. Repurification by cation exchange did not improve the reproducibility of the separations, possibly because impurities are reintroduced by the distilled water. Definite improvement was noted when the /sup 140/Ba was separated from /sup 140/ La and other hydrolyzable materials by residue adsorption methods. A calorimetric measurement of a salt sample over a period of 148 days gave a tritium half life of 12.361 plus or minus 0.028 years. This value confirmed the earlier value of l2.355 plus or minus 0.028 years. The /sup 208/Po--/sup 209/Po mixture returned from Argonne National Laboratory is being processed further. Two batches of polonium-contaminated organic material were wet-ashed in nitric and perchloric acids. Further purification will be by techniques similar to those presently used for separating /sup 210/Po from bismuth. An unidentified gamma activity was found in the polonium that was recovered from pieces of Monel fluorination apparatus. The optimum …

Progress in the development of the Sioux Falls Power Reactor is reported. Information is presented on: reactor physics of first core high-enriched boiler fuel elements; design and performance testing of in-core ion chambers, calibration wire, and monitoring system; testing and inspection of core components; irradiation testing of reactor vessel material; instrumentation development; and startup testing program. (N.W.R.)

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The on-line system for simultaneous data collection from two physically unrelated neutron time-of-flight experiments is described. A transistorized, digital computer with a 2048, 24 bit word memory provides 1024 and 256channel time analyzers, clocks, and total events and monitor scalers for fast and slow neutron chopper experiments, respectively. (D.C.W.)

The design of the Experimental Gas-Cooled Reactor fuel assemblies is described and a brief outline of the experimental heat transfer and fluid dynamic studies and mechanical testing is given, and he results of their application to the fuel element analysis are shown. The failure criteria are presented, the hot-channel factors are described, and the expected fission-gas pressure buildup within the elements is discussed.

When the Brookhaven AGS started operation in the summer of 1960 very little experience with targeting in strong focusing proton synchrotrons was available. While it was evident that targeting techniques would differ markedly from those used in weak focusing machines, only actual running experience would set the proper parameters for a truly satisfactory targeting system. It was, therefore, an advantage that temporary targeting devices were used initially. Work on a more permanent system was not started until the summer of 1961, and the first component of the system installed in January 1962. While further refinements are still continuing the essential features of this targeting system have now sufficiently proven themselves in actual operation to remain unchanged. This system in its present form is the subject of the first portion of this paper.

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Declassified 30 Aug 1973. 125 figures are included which were presented at the Materials Review Meeting for the LCRE, SNAP-50/SPUR, and Advanced Materials programs, held at CANEL on Sept. 18 and 19, 1983. Fuels, structural materials. alkali metal coolants, and auxiliary materials are included. (DLC)

The BNL cold neutron facility has been used to obtain inelastic scattering cross section data from three first-row transition elements, titanium, vanadium, and nickel, and a random binary alloy Ti.67-Zr.33. From the data, we have computed vibrational frequency distributions exhibit peaks corresponding to major critical points. A comparison of the distributions from the different samples leads to the following conclusions: 1) The shape of the frequency distributions of the b.c.c. metal (V) and f.c.c. metal (Ni) are remarkably similar, the relative positions of the critical points being the same for both; 2) The frequency distribution of the h.c.p. metal (Ti), which has two atoms per primitive cell, shows structure corresponding to acoustical and "optical" modes of vibration; 3) The titanium-zirconium alloy has the h.c.p. structure, and its experimental frequency distribution is similar to that of titanium, except at low frequencies where alloying with the heavier mass zirconium atoms tends to smear out the peaks corresponding to acoustical modes. Measured frequency distributions were obtained for the titanium-zirconium alloy slightly above and below the critical temperature for the phase transition to b.c.c. structure. The frequency distributions in the two phases are different, the most striking feature being a shift of the high …

The subject of this paper is the experimental and technical aspects of the measurements of nuclear resonance parameters. I will confine my remarks to those reactions induced by low energy neutrons, i.e. neutrons of less than approximately 100 kilovolts. The bulk of these measurements have been performed by neutron time-of-flight techniques, and I will direct my attention to these techniques. The first half of this discussion will concern the apparatus with which these measurements are made; the second part will be a discussion of the various experiments by which these parameters are measured, with an emphasis in both areas of discussion on relatively recent developments in the field.

When the ``stop-gap`` rate-of-rise meter was installed on all 8 reactors by Amendment 1 to CGI-806 it was intended to replace it with a more satisfactory design when possible. Successful completion of the development program now permits installation of equipment of sufficient reliability to be utilized in the safety circuit. This document defines the program necessary to provide power rate-of-rise protection in the safety circuits of B, C, D, DR, F, H and KE Reactors, provides justification for the project., and presents estimates of the cost and schedule required to accomplish the program.

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Several evaluations of Harvey ``O`` size natural I&E aluminum components have been made. The performance of components received prior to May 1961, was unsatisfactory. To improve component quality, Harvey made major process modifications. Components processed at HAPO after July 1, 1961, were received subsequent to Harvey`s modifications, and met specifications. Procurement and evaluation of an additional 150,000 Harvey OIIIN components was authorized. Evaluation of the 5 first 150,000 Harvey OIIIN improved components suggested partial qualification. This document reports and makes recommendations based on the test data for Harvey improved components as of August 31, 1963.

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In response to an inquiry by Euratom, estimates of the costs for the production of 85 kg of 15% Pu-240 metal and for the production of 15 kg of 25% Pu-240 oxide at HAPO were recently requested by the Atomic Energy Commission. In connection with this inquiry, comments were requested regarding the possibility of establishing and measuring product plutonium oxide ``sinterability`` parameters. This report presents estimates of the costs for separations processing by the Chemical Processing Department for the cases of interest. Process ground rules and any necessary assumptions are explained. In addition, the problems of measuring oxide ``sinterability`` are briefly discussed. Highlights of this study were previously transmitted to the Irradiation Processing Department for incorporation in a formal reply to the original Commission request. Subsequently, some adjustments in ground rules have caused cost changes which are included in this report.

A description of the digital readout and drive portion of the Advanced Reactivity Measurement Facility II is presented along with the philosophy used in selecting the system block diagram and components, accuracy considerations, and a preliminary evaluation of performance and usability. The presentation discourages duplicating of the equipment; advantage should be taken of the opportunity to improve upon it. To this end guideposts are provided as well as a documentation of those aspects of the design that are considered worthy of duplication. (auth)

The main purpose of this report are to provide 1) a reference source for the interchange of analog engine model information with AGC, and 2) a reference point for future WANL analog model development. Being a model status report, the present state of the models are presents.

Two long-term test cells were fabricated and tested. One was loaded with a 30 UC--70 ZrC sample and the other with a 90 UC--10 ZrC samrple. The rates of vaporization of these samaples in vacuum were determined both in the absence and in the presence of a Ni anode maintained at 983 deg K with an electrode spacirig of 20 mils, hr order to set the baseline values. Measurement of the rates of vaporization of these samples under these conditions in the presence of Cs vapor at a pressure of about 1.8 torr are in preparation and will be continued for 1000 hr. Operation of the first test cell, containing the 90 UC- -10 ZrC emitter, was terminated after 510 hr because of leakage through a faulty metal gasket sealing the electron-gun compartment. The second test cell, containing a vapor-deposited W-clad UC emitter, was assembled and operated for a period of 111 hr. The test was terminated because a leak developed between the cell compartment and the electron-gun compartment. A control cell containing a solid W emitter is being assembled to check the modifications made in the design of the electron-gun channber and the filament in order to overcome such …

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