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The purpose of these investigations is to determine, grossly and simply, if a shock hazard exists from an explosive failure of the pressurizer vessel within the vapor container. Because of the geographical location of the reactor, an explosive failure which ruptured the vapor container might release radioactive contamination from the reactor to nearby inhabited communities. The study is considered more as a generic problem than of a specific design and is concerned with the shock hydrodynamics of an exploding steam vessel. (auth)

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The principal relations for the stress analysis of flat circular plates according to the classical theory are presented in a convenient form. Almost any flat circular plate of uniform thickness, with or without central holes, loaded with any combination of axisymmetrical loads may be analyzed by the procedures. (A.C.)

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This report details initial results of a large scale accountability test program which was recently carried out in the Redox Facility. The test, as originally planned which was to consist of the complete processing (no inventory-clean plant basis) of about 55 tons of selected metal in conjunction with an extensive analytical, sampling, and volume measurement program. With the exception of two incidents, the processing requirements (minimum inventory and measurement of all material) necessary to the success of the test, were met. The two incidents which increase the uncertainties associated with some of the material balance values obtained were: the discharge of an estimated 700 pounds of uranium to the floor in a transfer from F-5 to F-4 due tot he improper installation of the F-5 to F-4 transfer line (jumper) and the discovery of a large accumulation of plutonium ({approximately} 15 kg) in the L-2 stripping tower after completion of the test run.

It has been noted on occasion that the side rupture rate at lower exposure is higher than one would expect in order to be consistent with the mathematical model (Weibull curve) used describe the rupture data. This has apparently been due to a few ruptures occurring at exposures lower than one would anticipate on the basis of the model. Restricting themselves to fuel elements irradiated under similar conditions of power and temperature, it is difficult to assert that these ruptures are anomalous with respect to the model used since there are so few ruptures involved. For this reason, some means of combining data was called for in order to see whether or not at least some of these low exposure ruptures were inconsistent with the model, and, if so, to revise the model in order to better describe side rupture performance. In this report, the results of an analysis of side failure data for failures covered in a previous report are given. Also included is a discussion of possible implications derived from recognition of the existence of this revised model.

The development of a remotely operated device for determining the coalescence times of plant process streams suspected of containing surfactants such as silicic compounds and fission product zirconium compounds is described. A general correlation between the coalescence times of pilot plant extraction column aluminum nitrate feeds and 3.25 percent tributyl phosphate extractant streams and the observations of column behavior of these streams is demonstrated. The application of the coalescence test to plant streams is given. (auth)

It is the objective of this study to investigate preliminary expansion program requirements for process water, as supplied by 190 Building equipment; from the point of view of practical pumping, flywheel and pump suction head requirements. These requirements are to be determined at this time in such a form and accuracy as to be useful in refined estimating for budget study purposes. In order to obtain the objectives of this study at this time it has been decided to consider five different conditions of process water flow to a reactor. These conditions are flow to the reactor under summer conditions of operation in gallons per minute with a corresponding top of riser pressure in pounds per square inch: 85,000 gal/min, 580 psi; 100,000 gal/min, 480 psi; 130,000 gal/min, 280 psi; 150,000 gal/min, 280 psi; and 150,000 gal/min, 150 psi.

An earlier report suggested a double headwave method of generating a rarefaction first motion. In this method a geologic situation is selected so that energy that has been critically refracted once above the shot and once below shot arrives first. Since the theory of headwaves gives in the usual stationary phase approximation a ninety degree phase shift for each critical refraction, energy that has been critically refracted twice produces a 180 degree phase shift. Oil well data was presented to show that the necessary geologic situation exists in nature. A question has come up regarding the propagation of long wave lengths (16,000 ft) in the thin bed (3000 ft.) above the shot in the geologic situation cited in the earlier report. At the tine of writing of the report it was realized that the thickness of the bed should be considered in propagating the 3 to 5 wavelengths along the bed. The theoretical problem of propagation in high speed elastic bed has not been solved. The best information available at this time indicates that it might indeed be possible to go out into reef country and experimentally find a location suitable to generate a rarefaction first motion by the double …

Uranium and plutonium were recovered by liquid-liquid extraction from simulated sulfuric acid stainless steel decladding solution with several extractants. Consecutive extraction of U(IV) and Pu(III) or (IV) by 0.1 to 0 3 M primary amine in hydrocarbon-- alcohol diluent appeared promising, and chemical flowsheets were demonstrated in laboratoryscale continuous countercurrent extraction. Extraction of U(VI) with a dialkylphosphoric acid appeared promising when plutonium recovery is not needed. Recovery is also chemically feasible by extraction of U(VI) and Pu(IV) with an N-benzyl secondary alkyl amine or a trialkylphosphine oxide. The amine extracts are stripped with nitric acid, giving a sulfate-nitrate product solution. The organophosphorus extractants permit elimination of the sulfate but require sodium carbonate for stripping. (auth)

Bench-scale studies were made on use of di(2ethylhexyl)-phosphoric acid in an organic diluent (Dapex process) for solvent extraction recovery of vanadium from acid leach liquors. Vanadium may be stripped from the solvent by either acidic or alkaline reagents, the former having been studied in considerably greater detail. A process for single-cycle recovery and separation of uranium and vanadium from sulfate leach liquors was shown to be attractive both from the standpoint of operation and chemical costs. Process schemes for recovery of vanadium from uranium-barren liquors are also described. On the basis of the encouraging laboratory results, pilot scale tests for specific applications are recommended. (auth)

The design, fabrication, and installation of a fuel-element guide assembly for the Sodium Reactcr Experiment are described. Improvements in this assembly over other models are outlined, and recommendations for the testing of SRE core elements are presented. (T.F.H.)

Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ intermetallic compounds demonstrated good stability and fission gas retention capabilities. Developmental aluminum powder metal products showed good corrosion resistance at high temperatures while retaining excellent high temperature strength. All of the fuel compositions tested (UO/sub 2/, U/sub 3/O/sub 8/, and UAl/sub 3/ in aluminum matrices) exhibited density decreases under irradiation. Tensile tests on sandwich-type fuel plates at elevated temperatures indicated that the fuel plate strength is strongly influenced by the core material rather than dependent primarily on the cladding material as was found true of lower (MTR) temperatures. Three capsules containing beryllium were inserted in the ETR, in order to determine strength, gas release, and growth during a high-temperature (600--800 deg C) irradiation. An MTR fuel element employing advanced metallurgical techniques to optimize the hydraulic and heat transfer characteristics was fuily irradiated in the MTR. The fuel element consisted of 32 plates containing 250 g U/sup 235/ in a U/sub 3/O/ sub 8/--Al dispersion. A prototype ETR fuel element was made without side plates. (M.C.G.)

A detailed examination was made of one of three plutonium-238 fueled SNAP 3 heat sources which was shipped from Mound Laboratory in May 1961 and returned in May 1963,. Examination of source included radiography, calorimetry, dimensional inspection, radiation measurements, internal pressure measurements, metallographic examinations of the containers, and recovery and impurity analysis of the plutonium fuel. Results showed that the inner tantalum container of the source failed at the weld, allowing the plutonium to the escape and to attack the Haynes Alloy 25 outer container. Failure at the weld was attributed to the fact that the plutonium had become molten at some time during its use and to poor welding of the liner during fabrication of the source, and not to corrosion of plutonium on the tantalum. It was concluded that tantalum is a satisfactory container material for plutonium at temperature below the melting point of plutonium (640°C).

Declassified 6 Sep 1973. Information ia preaented concerning LCRE fuel, components, primary and refiector system, instrumentation, reactor materials; and SNAP-50/SPUR specifications, shielding, pumps steam generators, and materials. (DCC)

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Waste supernate stored in Tank 11H was analyzed periodically from May 1973-August 1975 to determine the rate of nitrite ingrowth by radiolytic decomposition of nitrate. This waste was transferred to tank 33F in accordance with TA 2-892, Rev. 1, 'Use of Cracked Tank for Fresh High Level Waste,' during the week of November 10, 1975. This letter summarizes analytical and corrosion characterization which indicate that this transfer should not increase the risk of stress corrosion cracking in F Area non-stress-relieved tanks. An interpretation of the nitrite ingrowth data is presented and used as a basis for cokncluding that the crack in Tank 11H occurred early in 1974. The formation of nitrite in waste supernate was followed for 2 1/4 years during the last filling and storage cycle in 11H. The conversion of nitrate to nitrite in the 1 1/2 year period after filling was 4.9 x 10{sup -11} mol NO{sub 2}{sup -}/{ell} BTU of fission product heat. The energy released during the period was 1.15 x 10{sup 10} BTU with a corresponding increase in nitrite of 0.56 mol/{ell}. The crack that was first observed in Tank 11H in April 1974 probably made its final penetration through the wall in March …

A simple analytic method is developed, based on physical approximations, for treating transient implosive longitudinal compression of bunches of heavy ions in an accelerator system for ignition of inertial-confinement fusion pellet targets. Parametric dependences of attainable compressions and of beam path lengths and times during compression are indicated for ramped pulsed-gap lines, rf systems in storage and accumulator rings, and composite systems, including sections of free drift. It appears that for high-confidence pellets in a plant producing 1000 MW of electric power the needed pulse lengths cannot be obtained with rings alone unless an unreasonably large number of them are used, independent of choice of rf harmonic number. In contrast, pulsed-gap lines alone can meet this need. The effects of an initial inward compressive drift and of longitudinal emittance are included.

Fluidized bed incineration and waste fixation processes are being used to process the types of wastes expected from nuclear fuel reprocessing and production plants. Test incineration runs have been made on two types of wastes: high efficiency particulate air (HEPA) filters and tributyl phosphate-solvent solutions. Laboratory-scale vitrification equipment was used to produce glass pellets from incinerator ash and blends of other expected waste streams. Computer modeling gave an expected product integrity life of over 2,000 years.

This report on the control program to minimize beryllium levels in Laboratory workplaces includes an outline of beryllium surface, soil, and air levels and an 11-y summary of sampling results from two high-use, high-explosive test firing bunkers. These sampling data and other studies demonstrate that the beryllium control program is functioning effectively.