Tin-- aluminum base coatings applied by a cold spray-hot vacuum diffusion technique were studied further on Ta-10 W and Ta-10 Hf-5 W and work initiated on Ta--30 Nb--7t/2 V. Refractory additions to the coatings were optimized for Ta--10 W and the use of aluminum-silicon in tin was found beneficial for Ta--30 Nb--7 1/2 V. Furnace and oxy-acetylene torch tests were performed at temperatures from 1100 to over 3000 deg F. Diffusion treatments in vacuum, hydrogen, and argon were compared for coatings on Ta-10 W. Oxide formation on Ta--10 W coatings at various temperatures was studied by x-ray diffraction. The oxidation behavior of various tin--aluminum alloys and of the intermetallic (Ta--30 Nb--7 1/2 V) Al/sub 3/ was also studied, together with interactions of three alloys with A/sub 2/O/sub 3/ at elevated temperatures in vacuum. (auth)

None

Research and development of water-cooled reactors are reported including work on EBWR and BORAX-V. Work on liquid metal cooled reactors is also reported in sections on general research and development, EBR-I and II, aud FARET. Other work is reported on genenal nuclear technology and advanced systems development. (J.R.D.)

A number of conceivable reactivity accidents were analyzed, using conservatively pessimistic assumptions and approximations, to permit evaluation of reactor safety. Most of the calculations, which are described in detail, were performed by a digital kinetics program, MURGATROYD. Some analog analyses were also made. None of the accidents which were analyzed lead to catastrophic failure of the reactor, which is the primary consideration. Some internal damage to the reactor from undesirably high temperatures could result from extreme cold- slug accidents, premature criticality during filling, or uncontrolled rod withdrawal. Each of these accidents could happen only by compounded failure of protective devices, and in each case there exists means of effective corrective action independent of the primary protection, so that damage is unlikeIy. The calculated response to arbitrary ramp and step additions of reactivity show that damaging pressures could occur only if the addition is the equivalent of a step of about 1% delta k/k or greater. (auth)

Considerable interest has been generated concerning the recent series of overbore fuel failures at C Reactor. It therefore is appropriate to document the operating conditions which existed prior to the failures. This report presents a chronological description of events leading up to the failures, and graphs and tables of various pertinent parameters.

Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added to the combined wash solution and filtrate produced during the precipitation step to destroy the formate ion (which inhibits uranium extraction) and to prevent post-precipitation during the evaporation of these solutions. The other flowsheet calls for addition of sufficient nitric acid to destroy the formate ion, but not enough to prevent post- precipitation during the concentration step. Post-precipitation removes additional zirconium and fluoride, but necessitates an additional solids- separation step. (auth)

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company.

The losses of charged particles from a detector aperture, due to multiple scattering of the particles in thin layers of material preceding the detector, are calculated with the aid of a high-speed digitai computer. The rootmean-square multiple-scattering angle is computed after the method of Moliere, and graphs are presented for protons and alpha particles scattering in nitrogen, aluminum, argon, copper, silver, and gold, and for deuterons and tritons scattering in aluminum and copper. The range of particle energy covered is from 5 to 100 Mev. A second program is used to construct a map from which losses, as a function of the root-mean-square multiple-scattering angle and the scattering configuration, may be directly read. The FORTRAN listings for both programs are given. (auth)

Hood 7-A will be used to handle filtrate and miscellaneous aqueous waste streams from the RMC button line. This document defines the critical mass control specifications for hood 7-A.

The critical-mass incident at Recuplex has necessitated resumption of reworking Task 1 supernatants through the Purex process. The supernatants contain relatively small quantities of plutonium and will be shipped as treated nitric acid solutions in PR cans. Current plans are to introduce the solutions into the Purex process at the normal rework position, the HAF Make-up Tank E6. This report summarizes the anticipated character of supernatant recycle material, outlines process control requirements and recommends procedures for assuring critical mass control within the limits of the current process control specifications.

A system for generating detailed tables of gamma ray cross section data has been devised for use on the IBM7090 computer. This sy;tem obviates the preparation of large amounts of cross section data. It also provides a scheme for rapid access to these tabulated values. (auth)

Openation of a 6-in.-dia foam separation column with Sr/sup 89/ tracer and dodecylbenzenesulfonate as a surfactant and foaming agent was continued. The catalytic oxidation of H/sub 2/, CO, and CH/sub 4/ was studied using a nickel- chromepalladium ribbon catalyst. A Mark I prototype fuel assembly was sheared to within 1.5-in. of the end by modifying the gas hydraulic system of the shear. The force required to shear a highly carburized Mark I fuel assembly ductile tubing. Demonstration of the mechanical dejacketing of the SRE Core I fuel burned to approximates 675 Mwd/ton and cooled about 2 years is complete, and decontamination and equipment removal from the segmenting cell is approximately 90% complete. Ten SRE Core I fuel jackets were dissolved in aqua regia and analysis showed negligible U and Pu. A semicontinuous leach run, in which -2 mesh graphite fuel containing 2.6% U was leached in 90% HNO/sub 3/ at 60 deg C, gave only 0.37% U loss. Graphically estimated spectral factors for radiation between tubes within fuel bundles and improved wall radiation factors were rised to calculate the temperature distribution expected within spent fuel elements. Further studies of the dissolution of zirconium oxide by HF in fused salt resulted …

The Pebble-Bed Reactor Experiment (PBRE) was designed to advance the pebble-bed concept by providing a test of characteristic features and make contriliutions to the general development of all-ceramic gas-cooled reactors. The following objectives were established for the reactor experiment: to investigate key features of the pebble-bed concept, including on-stream fuel handling, movement of fuel through bed, and performance of core; to obtain operation and maintenance experience with a system contaminated with fission- product activity; and to investigate the behavior of graphite fuel elements. A fourth objective, study of the behavior of core materials at conditions occurring with exit gas temperatures in the range 2000 to 2500 deg F, was tentatively included. The preliminary design oE a 5-Mw(t) reactor for achieving these objectives was prepared. The core of the PBRE is a 2 1/2-ft-diam, 4-ft-tall cylinder containing approximately 12,000 spherical graphite fuel elements 1 1/2 in. in diameter. Fuel spheres are added to and removed from the core by gravity flow, and these operations are performed while the reactor is at power by using pairs of valves for passage of elements into and out of the high-pressure system. Exposed fuel can be recycled to the top of the core. Helium coolant …

The development of the system and techniques to permit determination of strains at right angle to the axis of loading in the specimen was continued. An additional optical system was developed to accept the lateral image of the gage points and project a vertical image of the same proportion to the apertures of the strain analyzer. Using a dummy specimen of steel in the load train, the automatic pressure control system for the gas-bearing universals was operated. A fluctuation of gas pressure occurred within the bearings. Multiple progressive fracture planes were observed throughout the gage length of fractured graphite and tungsten. (M.C.G.)

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the County Auditor can approve for payment a claim by a Court Reporter for a transcript made of Grand Jury proceedings under the following facts.

The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element are presented. The tests were performed to investigate the possibility of damage to such long thermal-time-constant fuel rods when subjected to short-period power excursions, and to test the effectiveness of an instrumentation technique for measurement of UO/sub 2/ fuel temperatures within the rods. In an initial series of power excursion tests, in which the range of reactor periods was from approximately 1 sec to 7.5 msec, simultaneous measurements were made of the transient temperature at the center of the fuel rod and at the outer cladding surface. Fuel rod rupture occurred during the exponential rise of the 7.5-msec excursion. Similar short-period tests performed on a second fuel rod contain ing no internal thermocouples did not result in cladding failure, supporting the postulation that rupture of the first rod was caused by waterlogging of the UO/sub 2/ as a result of the cladding penetrations made for installation of the internal thermocouples. Calculations of the transient temperature distribution in the fuel rod were made, and the results are found to be in good agreement with the experimental data obtained on the central-UO/sub 2/ and cladding-surface …

This technical report details and outlines the BGRR facility's operations and performance record over a period of twelve years. The author of this report finds that the reactor is "one of the most stable and dependable in the business." The report includes two figures.

We are enclosing three copies of a proposal concerned with the preparation for preliminary evaluation of up to 128 Hanford CV size I and II fuel elements to determine an optimum gas-pressure-bonding cycle for the fabrication of this type of fuel element. This proposal is based on your request as outlined in your letter dated May 7, 1962, and document No. HW-72417. Included is a cost estimate of the funding required to conduct this experimental study. All of the aluminum-clad uranium fuel assemblies are to be prepared and furnished by HAPO for gas-pressure bonding at Battelle in existing equipment. To implement the proposed program we have also enclosed six copies of the BMI-AEC research agreement (Serial No. 88). The agreement provides for a six-month research period with an estimated total cost of $24,780. This sum includes $1,180 find fee as established in Contract No. W-7405-ENG-92. Receipt of two fully amounted copies of the agreement, classification guidance, and the specimens will allow us to proceed.

None

This test is identical to the original except that it authorizes the performance of a trial reduction in reactor flow during a prior reactor shutdown. This trial flow reduction will be performed in the same manner as proposed for the actual test, with one exception. This is, that based upon the results of this preliminary test some changes in the timing of the different steps may be indicated. Such changes can readily be handled by making each step dependent upon the observed reactor outlet temperature during the test performance. The other significant change in the production test is the increase in the allowable bulk outlet temperature from Ti + 40 {plus_minus} 3{degrees}C{sup *}. This change is needed to obtain a reasonable extrapolation of the results of tests No. 1 and No.2 to 90{degrees}C, and is justified from a hazards standpoint by the excellent flow control achieved during test No. 1 and by the trial test that will be run prior to the performance of the actual test No. 2. Other aspects of the test basis and justification are presented in the original production test.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether Certificates of Deposit in Banks are "Lawful Money of the United States."

We present the results of measurements of the angular distribution of fission fragments produced by irradiation of Au{sup 197} and Bi{sup 209} with various heavy ions. The projectiles, B{sup 11}, C{sup 12}, N{sup 14}, and O{sup 16}, had energies from a few MeV above the Coulomb barrier to 10.4 MeV per nucleon. The gross features of these results can be explained by use of a model and parameters that have been used by others to account for angular distributions of fission fragments from helium-ion bombardments. In detail, however, these results appear to indicate that the models used to predict the average value of the angular momentum of the compound nucleus give values too low near the Coulomb barrier. Furthermore, at high bombarding energies it is necessary to consider the fact that appreciable direct interaction is taking place.

From Introduction: "The work of the Magnetic Measurements Section of the National Bureau of Standards includes (1) testing of specifically prepared test specimens intended for use as standards for checking magnetic testing apparatus (2) investigation and development of magnetic testing apparatus (3) calibration of mutual inductors, test coils, and instruments for measuring magnetic fields, and (4) investigations in the field of magnetics such as studies of phenomena associated with nuclear magnetic resonance or the selection and testing of materials suitable to be used as standards of magnetic susceptibility."

This report, from the Chemical Processing Department at HAPO, for April 1962 discusses the following: Production operation; Purex and Redox operation; finished products operation; maintenance; financial operations; facilities engineering; research; employee relations; special separation processing; and auxiliaries operation.