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

Proposed fuel element loading and operating conditions for this test are tabulated. The loading is designed to provide high tube power and near-maximum-allowable coolant outlet temperature, accompanied by low fuel surface heat fluxes. Conditions which would exist during the proposed test were compared with those during the rapid depressurization incident in KER-2 on Jan. 31, 1960.

Computational results for the characteristic values and solutions of Bessel's equation are presented. Specifically, the results pertain to the first two solutions subject to the Neumann boundary condition at r = a,b and to the first solution subject to the Dirichlet condition, when (b-a)/(b+a) is small (0.1, 0.01, and 0.001). Approximate analytic formulas are derived to complement the computational results. The possible application of the data to phenomena involving the interaction of an intense circulating beam and the electromagnetic fields within a particle accelerator is indicated, as is also the utility of the results for estimation of the loss-factor, Q, for resonant electromagnetic modes of possibly high order within a toroidal vacuum chamber of rectangular cross section. (auth)

Reactor design information obtained from 3 years' operation of a small pressurized-water reactor, the SM-1 (formerly APPR-l), is presented and discussed. The SM-1 reactor, designed to produce 10 Mw(t) power, employs fully enriched uranium fuel in the form of UO/sub 2/ dispersed in stainless-steel fuel plates. The reactor is cooled by water at 1200 psia and mean temperature of 44) deg F. Core-physics measurements were performed of temperature coefficient, pressure coefficient, rod calibration, stuck rod position, and transient xenon as a function of core burn-out. Core burn-out characteristics were compared with few- group calculations, and reasonable agreement was obtained. Thermal-heat-balance data were obtained on the reactor core. The temperature pattern in the nominal and hot channels under operating conditions was calculated. These calculations indicated that certain of the fuel channels operated in the nucleate boiling regime. Examination of one of the fuel channels suspected of nucleate boiling indicated no adverse effects. The system response to load perturbations and during pump coast-down was measured utilizing plant instrumentation. This response was compared with analytical predictions using a lumped kinetic model, and reasonable agreement was found. Both neutron and gamma traverses were made through the primary shield during reactor operation. Gamma traverses were …

The scintillation and Cherenkov properties of UVA (ultraviolet absorbing) and UVT (ultraviolet transmitting) Plexiglas specimens were tested by analyzing cosmic-rayinduced pulses traversing the materials. It was found that the UVT sample has less than 1/6 the scintillation effect of UVA and is preferred for use in counters. (J.R.D.)

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Calculations of critical size, reactivity coefficients, and delayed neutron fractions are described for mockups of a plutonium-fueled EBR-I (Mark IV) and five possible metal-fueled power reactors. The calculations for critical size were performed using the SNG transport-theory code. The reactivity coefficients were estimated by SNG calculations or by one-group perturbation- theory desk calculations. The delayed-neutron fractions were estimated by an approximate method, which starts with a calculation of beta for a bare core and then makes a correction for the small effect of the blanket. The reactivity effects studied were the effects of fuel-plate and whole-core expansion and control-rod worths. (auth)

This specification covers the furnishing of piping, piping accessories, and certain specified mechanical equipment. Further it covers the provision of all labor, supervision, supplies, equipment and tools required for the handling, installation, painting, readying for operating and functional testing of all the equipment and systems described.

In the first section of this report, a study was made of the high- temperature properties of a Mo-3% Th alloy to determine whether this alloy should be rejected as valueless or a full research program should be proposed. Results of this investigation show that thorium should be studied more intensively as an alloying addition for molybdenum. In the second section, an evaluation is presented of the oxidation behavior, mechanical properties, and cladding properties of Nb - 55 at.% Zr - 5 at.% Ti alloy. (W.L.H.)

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The feasibility of cold extrusion for Zircaloy-2 tube production was studied and the basic feasibility of cold extruding Zircaloy-2 was indicated. Lubrication systems, composed of a lubricant and a conversion coating, were developed and evaluated for the current application. A fluoride-phosphate base coating and a number of promising lubricants were selected for actual extrusion tests. Bars of Zircaloy-2 were successfully cold-extruded to reductions of 50, 65, and 80%. The best lubricants provided excellent surface finish, and no evidence of cracks or other defects could be found in the specimens. Annealed extraded specimens exhibited the same tensile properties as annealed raw stock. Deformation efficiency was found to be in the same range as for cold-extruded aluminum, titanium, and steel. Cold extrusion of Zircaloy-2 heavywalled tube shells was also found to be economic if sufficient production volume exists. (P.C.H.)

Selected physical and biological data bearing upon the environmental variations created by nuclear explosions are presented. Emphasis is placed upon the early consequences of exposure to blast, thermal radiation, and ionizing radiation to elucidate the comparative ranges of the major effects as they vary with explosive yield and as they brief definitions of the terminology employed is followed by a section that utilizes text and tabular material to set forth events that follow nuclear explosions and the varied responses of exposed physical and biological materials. Finally, selected quantitative weapons-effects data in graphic and tabular form are presented over a wide range of explosive yields to show the relative distances from Ground Zero affected by significant levels of blast overpressures, thermal fluxes, and initial and residual penetrating ionizing radiations. However, only the early rather than the late effects of the latter are considered. 52 references. (auth)

The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results …

A training course was held to familiarize members of radiological assistance teams from various parts of the U. S. with the origin and nature of situations that might, by the event of an unusual accident. release radioactive materials to a populated environment. The course consisted of a series of lectures and a tour of some of the radiation monitoring, source handling, and transportation facilities at NRTS. A summary of the lecture material is presented. (W.D.M.)

Strain gage instrumentation is reported of three Cowboy shots to measure the strain produced in salt by coupled and decoupled detonations. Linear array tests were made to develop a propagation law for strain, to determine particle velocity and acceleration in salt, to compare explosives, to determine the effect of impedance coupling between explosive and rock, and to investigate other seismic effects. Crater tests were made to determine the dynamic tensile breaking strength of salt. Tests were made to measure in situ, longitudinal (P) and shear (S) wave velocities and to calculate the dynamic elastic constants therefrom. Laboratory tests on core were made to determine the dynamic compressive and tensile breaking strength of salt. Physical properties tests were made under laboratory conditions for comparison with dynamic results. (W.L.H.)

Research in theoretical and experimental physics is summarized. The method of Wyse and Mayall for estimation of density distributions in stellar galaxies from observed rotational velocities was extended to a more realistic model. Methods of calculating pair production or bremsstrahiung cross sections are discussed. The presence of 10 previously unreported gamma rays was observed in the decay of Ag/sup 1//sup 1//sup 3/. The photoproton yield from Be/ sup 9/ was investigated. Theoretical studies were made of a proposed new type of electron muitlplying discharge. The Scebeck coefficients of several single crystals of Mg/sub 2/Si were measured from 7 to 1000 deg K. New data were obtained on the resistivities and Hall coefficients of Mg/sub 2/Si. A new technique for measuring the thermal diffusivities of soilds was devised. A dynamic pulse-heating method was developed for measuring the specific heats of metal wires from room temperature to 1000 deg C. The specific heat of copper was determined. Methods for measuring microwave Hall mobillties in semiconductors were improved. The resistivity of sodium tungsten bronze as a function of sodium composition was obtained down to 4 deg K. Studies are being made of the frequency dependence of the resistance and capacitance of samples of …

A description is given of the safety features and the major alterations to be performed prior to occupancy. The evaluation was made in support of fubrication work on the production of safe isotopic power sources from Cm/sup 242/ and Sr/sup 90/. The chemical, nuclear, and radiobiological properties of Cm/sup 242/ and Sr/sup 90/ are outlined. The projected physical fiow of materials for production of the isotopic power souroes is schematically given. An evaluation of the malfunctions, operational hazards, and remedial health physics procedures is presented. The analysis and evaluation of postulated maximum credible incidents are demonstrated. (B.O.G.)

This report was prepared as text material to serve as a basis for a series of lectures for the Interational Institute of Nuclear Science and Engineering, Argore National Laboratory. Radioactive waste disposal is discussed, including origin and management of wastes; handling of gaseous, solid, and liquid wastes; reduction of liquids to solids; release of wastes to environment; ultimate disposal; and future problems. Extensive data tabulations are presented. (136 references). (T.R.H.)

Specifications are given for the fabrication of Al--Pu alloy pins clad in aluminum. The cladding components were loy pins clad in alummum. The cladding components were fabricated from 1100 aluminum, 1/16 in. in diameter. End caps were fabricated from the same material by a series of passes through draw plates to 0.035-in. diameter. The core material was cast as cylinders 0.375 in. in diameter and approximately 2 in. long in a heated graphite mold. The alloy composition was 15.75 wt.% plutonium. Billets 1/4 in. long were cut from the cylinders. These were extruded through an 87 to 1 reduction in area to a final size of 0.032 plus or minus 0.001 in. For loading, the cans were inserted in a lucite fixture and placed in an open-front hood, the cores dropped in, and the can opening scrubbed with ethyl alcohol. The 0.035-in. diameter end cap wire was then pressed into the can opening until it contacted the core and was cut off level with the top of the can. Sealing of the final end was done by fusion welding using alternating current with the tungsten inert gas process. (W.L.H.)

This review covers research on irradiation effects, sintering of oxides, mechanical and physical properties of materials, film gages, hydrodynamics, and fuel elements. Separate abstracts have been prepared for the 10 papers. (W.L.H.)

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The Turret reactor program will study the practical effects on both the reactor and the coolant system of using porous, unclad fuel elements. In pursuit of this fundamental objective, efforts will be directed toward detailed study of the following points: (1) the behavior of unclad, porous graphite fuel elements at high temperatures under operating reactor conditions with respect to release of fission products and with respect to the degree of burn-up of uranium which may be practicably achieved in fuel elements of this general nature; (2) the operation of a hightemperatare coolant loop highly contaminated with fission products (specifically, the nature of the fission products deposited, mechanisms of deposition, and effects of various types of sunfaces and flow parameters, as well as maintenance techniques and applicable methods of fission product removal); (3) the basic requirements and effectiveness of gas-coolant purification systems for closed-cycle contaminated gas loops of this nature; and (4) the degree to which low-cost, chemically and mechanically simple fuel- reprocessing methods may be applied to fuel elements of this general character. Developments are summarized on the reactor, coolant system, gas-cleanup system, reactor facility, and materials. (W.D.M.)

The scale deposit on the Experimental Boiling Water Reactor fuel plates can be removed by slurry honing the plates with an abrasive-water mixture. Problems inherent in any production operation of this type are discussed. Areas of continued investigation of the method are suggested. (auth)

A description of the TREAT facility is presented. The static characteristics of the reactor which pertain to its dynamic behavior, such as temperature coefficient and prompt-neutron lifetime, are discussed. Also considered are other phenomena, the analyses of which provide some measure of the general adequacy of the calculational techniques employed. The correlation and analysts of transientexperiment results on this clean-geometry reactor are examined in considerable detail. In addition, an extrapolation of the reactor's performance beyond the present low design limitation of 400 deg C maximum local temperatare is included. (auth)