Results of an estimate of the waste management costs of the commercial high-level waste from a 3000 metric ton per year reprocessing plant show that the judicious use of the ceramic waste form can save about $2 billion during a 20-year operating campaign relative to the use of the glass waste form. This assumes PWR fuel is processed and the waste is encapsulated in 0.305-m-diam canisters with ultimate emplacement in a BWIP-type horizontal-borehole repository. The estimated total cost (capital and operating) of the management in the ceramic form is $2.0 billion, and that of the glass form is $4.0 billion. Waste loading and waste form density are the driving factors in that the low-waste loading (25%) and relatively low density (3.1 g/cm/sup 3/) characteristic of the glass form require several times as many canisters to handle a given waste throughput than is needed for the ceramic waste form whose waste loading capability exceeds 60% and whose waste density is nominally 5.2 g/cm/sup 3/) characteristic of the glass form requires several times as many canisters to handle a given waste throughput than is needed for the ceramic waste form whose waste loading capability exceeds 60% and whose waste density is nominally …

The report contains two major sections: Section I - An Improved Polyphase Ceramic for High-Level Defense Nucleation Waste reports the work conducted on titanium-silica based ceramics for immobilizing Savannah River Plant waste. Section II - Formulation and Processing of Alumina Based Ceramic Nuclear Waste Forms describes the work conducted on developing a generic alumina and alumina-silica based ceramic waste form capable of immobilizing any nuclear waste with a high aluminum content. Such wastes include the Savannah River Plant wastes, Hanford neutralized purex wastes, and Hanford N-Reactor acid wastes. The design approach and process technology in the two reports demonstrate how the generic high waste loaded ceramic form can be applied to a broad range of nuclear waste compositions. The individual sections are abstracted and indexed separately.

The ceramics process flow diagram has been simplified and upgraded to utilize only two major processing steps - fluid-bed calcination and hot isostatic press consolidating. Full-scale fluid-bed calcination has been used at INEL to calcine high-level waste for 18 y; and a second-generation calciner, a fully remotely operated and maintained calciner that meets ALARA guidelines, started calcining high-level waste in 1982. Full-scale hot isostatic consolidation has been used by DOE and commercial enterprises to consolidate radioactive components and to encapsulate spent fuel elements for several years. With further development aimed at process integration and parametric optimization, the operating knowledge of full-scale demonstration of the key process steps should be rapidly adaptable to scale-up of the ceramic process to full plant size. Process flowsheets used to prepare ceramic and glass waste forms from defense and commercial high-level liquid waste are described. Preliminary layouts of process flow diagrams in a high-level processing canyon were prepared and used to estimate the preliminary cost of the plant to fabricate both waste forms. The estimated costs for using both options were compared for total waste management costs of SRP high-level liquid waste. Using our design, for both the ceramic and glass plant, capital and operating …

The FRAN prompt burst reactor began operation at NTS on November 1, 1962 and continued in use until April 1965. From January 2, 1963 to August 12, 1964, an individual periodically performed maintenance and troubleshooting functions on various components of the FRAN reactor system. In June, 1980, the individual requested a review of the radiation dose that he received from his involvement with the FRAN reactor. An evaluation of the individual's radiation dose associated with the FRAN reactor operation was performed. This report details the reevaluation of the individual's estimated radiation dose from the FRAN reactor assembly, as derived from computer calculations, GODIVA-IV measurements, personnel dosimetry results, and a reconstruction of work scenarios.

Coupled electron-photon transport calculations have been carried out to simulate the photon generation when a 5- or 50-MeV electron beam strikes a solid or gas target. Results indicate that a 5-MeV beam striking targets of tungsten wire, air, or air doped with Kr or Xe generates a photon spectrum sharply peaked in the forward direction and with approximately 1/E spectral intensity. At right angles to the beam the photon intensity is predominantly due to characteristic K x-rays. A 50-MeV beam striking the same targets generates substantially higher photon yield in the forward direction, but the yield normal to the beam is similar to that due to the 5-MeV beam. However, positron-electron annihilation radiation constitutes a significant part of the photon radiation normal to the beam, and is more intense than characteristic K x-rays when the target is more than about one-third of the electron range.

The objective of this work is to quantify the changes which occur in the magnetoresistivity of coppers (having various purities and pretreatments, and at magnetic fields up to 12 T during the course of sequential fusion neutron irradiations at about 4/sup 0/K and anneals to room temperature. In conjunction with work in progress by Coltman and Klabunde of ORNL, the results should lead to engineering design data for the stabilizers of superconducting magnets in fusion reactors. These magnets are expected to be irradiated during reactor operation and warmed to room temperature periodically during maintenance.

A method is reported here for the analysis of I-129 in decontaminated defense waste salt solution at concentrations as low as 0.14 pCi/ml. Repeated analyses have been unable to confirm the presence of I-129 in decontaminated samples of Tank 24 supernate.

Ground samples of three nuclear melt glasses from underground nuclear explosions at the Nevada Test Site (NTS) were leached at 25/sup 0/C with natural ground water from NTS. Using our dynamic single-pass flow-through leaching system we monitored the release of radionuclides from the glasses during 420 days of leaching. We continually flowed the ground water over the melt glass at flow rates of 185 ml/day for half of the samples and 34 ml/day for the rest. Leachate solutions were collected continuously, and composite samples, collected on days 1, 2, 3, 6, 11, 32, 38, 70, 120, 230 and 420, were analyzed using low-background Ge(Li) gamma spectrometers. For most of the radionuclides the leach rate decreased smoothly throughout the experiment. Except for /sup 95/Zr, /sup 144/Ce, and /sup 155/Eu, there was no difference between the fast (185 ml/day) and slow (34 ml/day) flow-rate leach rates. The measurable leach rates ranged from a high of 1 x 10/sup -2/ g-glass/m/sup 2/ day for /sup 22/Na (slow flow-rate, day 1 in glass No. 2) to a low of 1 x 6/sup -6/ g-glass/m/sup 2/ day for /sup 54/Mn (slow flow-rate, day 420 in glass No. 2). Most of the leach-rate values were about …

The present invention relates generally to metal foils and methods of making the same. More particularly, this invention pertains to the fabrication of very thin, unbacked metal foils.

The definition of a time-dependent spectrum registered by an idealized spectrometer responding to a time-varying electromagnetic field as proposed by Eberly and Wodkiewicz and subsequently applied to the spectrum of laser-induced fluorescence by Eberly, Kunasz, and Wodkiewicz is here extended to allow a stochastically fluctuating (interruption model) environment: we provide an algorithm for numerical determination of the time-dependent fluorescence spectrum of an atom subject to excitation by an intense noisy laser and interruptive relaxation.

The parameter B/sub e//nr/sub p/ (here, B/sub e/ is applied magnetic field strength, nr/sub p/ is the plasma density-radius product) is proposed as a key parameter for spheromak heating studies. If B/sub e//nr/sub p/ is too large, increased magnetic fluctuations limit heating; low B/sub e//nr/sub p/ value results in excessive radiation losses. An optimum range appears to be B/sub e//nr/sub p/ approx. 1 to 5 x 10/sup -20/ Wb.

We have completed both the installation of the demonstration project and the assessment of the stream flows in Watauga County, North Carolina. The 17 kW, high head (178'), project on Laurel Creek in Watauga County has produced about 60,000 kWh over its first nine months of operation despite some electrical and other problems. It is currently producing 16 to 17 kW on a steady basis and is functioning as a popular site for visits by people who plan to install their own similar plants in areas throughout the Southeast. The stream assessment proved to be less satisfactory than the subsequently developed method for predicting long term stream flows. The latter method has been applied to all western North Carolina and this report presents its general conclusions.

A program was undertaken to identify an acceptable alternative to Dapon 35, an o-diallyl phthalate (DAP) prepolymer no longer available. Three o-DAP prepolymers from the Osaka Soda Company and four laboratory-scale prepolymers from Bendix-Kansas city were characterized and evaluated in DAP-fiberglass molding compounds. Gel permeation chromatography results for the Osaka prepolymers showed all three to be very close to one another in molecular weights (mw) and mw distributions, but slightly lower in both than Dapon 35. They are also slightly higher in monomer content. All three processed readily into DAP-fiberglass molding compounds and passed required physical property tests. One Osaka prepolymer was compounded into both asbestos and Orlon-DAP compounds on a production scale. Both compounds have passed all certification tests. The Bendix prepolymers were deliberately varied in mw and mw distribution and higher in monomer content than Dapon 35. Processing difficulties were encountered with both the lowest and highest molecular weight compounds, and the lowest molecular weight compound failed a number of physical property tests. The two intermediate molecular weight compounds processed readily and passed property tests. Guidelines were established for acceptable o-DAP prepolymers: (1) weight average mw (relative to polystyrene standards): 30,000 to 150,000; (2) mw distribution: 3.0 to …

The Seismic Safety Margins Research Program (SSMRP) is developing a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis and design process and explicitly accounts for uncertainties inherent in such a process. In Phase I, the seismic input, the soil-structure interaction, dynamic response of structures and subsystems, and fragility were developed and combined using a probabilistic computational procedure. Demonstration calculations were completed for the Zion nuclear power plant. In Phase II, presently ongoing, additional models, improvements to existing models, and improvements to the probabilistic computational assessment of Zion have been developed. Local site amplification has significant effect on structural response and is a major source of uncertainty. As part of the final Zion analysis in Phase II, an assessment of the local site effect at the Zion site was made using new time histories modified for the Zion soil conditions. In this paper, we briefly describe the approach used to correct the seismic hazard curve and time histories developed in Phase I for local site effects and discuss in some …

Experiments have begun on the Tandem Mirror Experiment Upgrade (TMX-U) using electron-cyclotron resonant heating (ECRH) to generate the hot electron populations required for thermal barrier operation (Energy E/sub eh/ approx. 50 keV, density n/sub eh/ < 5 x 10/sup 12/, and hot-to-cold fraction n/sub eh/n approx. 0.9). For this operation, rf power produced by 28-GHz gyrotrons is injected with extraordinary mode polarization at both fundamental and second harmonic locations. Our initial experiments, which concentrated on startup of the hot electrons, were carried out at low density (< 1 x 10/sup 12/ cm/sup -3/) where Fokker-Planck calculations predict high heating efficiency when the electron temperature (T/sub e/) is low. Under these conditions, we produced substantial hot electron populations (diamagnetic energy > 400 J, E/sub eh/ in the range of 15 to 50 keV, and n/sub eh//n > 0.5).

These studies indicate that ICRF transition pumping is feasible in the TMX-U experiment using moderate frequencies and power levels. Some degree of latitude must be included in the final design to compensate the rough calculations. The possibility of coupling near 2 ..omega../sub ci/ is attractive but awaits a clearer exposition of the theory and an adequate computer code.

An ion-cyclotron range of frequencies (ICRF) heating system has been installed in the Tandem Mirror Experiment-Upgrade (TMX-U) central cell. Our initial objective is to heat low density ions in the near field of the antenna. This heating reduces the collisionality of central cell ions, which decreases the filling rate of the thermal barrier by passing ions from the central cell. From power- and particle-balance calculations, we determined that 60 kW of absorbed power is sufficient to heat plasma densities of up to 2 x 10/sup 12/ cm/sup -3/. These power requirements are consistent with ion heating results from the Phaedrus tandem mirror. Based on this, we have installed a 200-kW oscillator/power amplifier, tunable to as low as 1.5 MHz. It drives a 110/sup 0/, 9 1/2-turn loop antenna that has a commercially built Faraday shield and matching network. The system has been tuned with plasma and is being used for the initial heating studies at the ion-cyclotron frequency ..omega../sub ci/.

The overall objective of the Westinghouse coal gasification program is to demonstrate the viability of the Westinghouse pressurized, fluidized bed, gasification system for the production of medium-Btu fuel gas for syngas, electrical power generation, chemical feedstocks, or industrial fuels and to obtain performance and scaleup data for the process and hardware. Technical progress summaries and reports are presented for the following tasks: (1) process development unit (PDU) test operations and results (gasifier test TP-033-1 and maintenance and modifications); (2) process analysis (environmental characterization results, coal gas combustion results, and fines elutriation and consumption results); (3) cold flow scaleup (modifications and maintenance, operations, and data analysis); (4) process and component engineering and design (hot fines recycle modifications, and hot recycled fines); (5) laboratory support studies (gas-solids flow modeling and coal/ash behavior). 23 figures, 23 tables.

An evaluation was made of the design and hydromechanical performance characteristics for three basic turbine types: axial flow (Jonval), inward radial flow (Francis) and crossflow (Banki). A single commercially available turbine representative of each type and within the appropriate power range (<5hp) was obtained for evaluation. Specific turbine selections were based on price, availability and suitability for operation at heads of 50 feet or less and flows under 2 cubic feet per second. In general, the peak operating efficiencies of each unit tended to be lower than anticipated, falling in the range of 40 to 50%. With sufficient flow, however, significant useful power outputs up to 3 hp were obtained. While the radial flow turbine (a centrifugal pump operated as a turbine) had the lowest initial unit cost, the axial and cross flow designs exhibited more stable operation, particularly under transient loadings. The crossflow turbine had the added advantage that it was essentially self-cleaning. With further developmental effort and appropriate design modifications it should be possible to bring each of these microhydro designs to their full performance potential.

Cobalt activation calculations will be reviewed, and similar comparisons of sulfur activation interior to electrical insulators on power transmission lines will be discussed. The relationship between neutron tissue kermas one to two kilometers from hypocenter and the particular activations of cobalt and sulfur are reviewed. At present, measured and calculated quantities agree within associated uncertainties, which are substantial. Additional work to shrink these uncertainties will be discussed. Particular cobalt activation topics will include: the sensitivity to thermal neutrons outside the pillar; calculated values using actual Nagasaki concrete composition; and calculational advances to improve modelling of the actual configuration. Particular sulfur activation topics will include: absolute comparisons of measured and calculated ratios of dpm/gm of /sup 32/P at all measured ranges, based on approximate experimental values for insulator attentuation and source radiations; the relationship between sulfur activation within a kilometer of hypocenter and kermas at two kilometers; and calculational advances to improve modelling of the actual configuration.

The equipment and methods used to recover and purify 339 g of thorium-230 and 890 mg of protactinium-231 from 22 of the 1251 drums of Cotter Concentrate are described. The process developed was (1) dissolution at 100/sup 0/C in concentrated nitric acid and dilution to 2 to 3 molar acid, (2) filtration to remove undissolved solids (mostly silica filter aid), (3) extraction of uranium with di-sec-butyl-phenyl phophonate (DSBPP) in carbon tetrachloride, (4) extraction of both thorium and protactinium with tri-n-octylphosphine oxide (TOPO) in carbon tetrachloride followed by selective stripping of the thorium with dilute of sulfuric acid, (5) thorium purification using oxalic acid, (6) stripping protactinium from the TOPO with oxalic acid, and (7) protactinium purification through a sequence of steps. The development of the separation procedures, the design of the pilot plant, and the operating procedures are described in detail. Analytical procedures are given in an appendix. 8 figures, 4 tables.

A single pass, tapered electron wiggler and associated beam transport has been constructed at the Experimental Test Accelerator (ETA) at Lawrence Livermore National Laboratory (LLNL). The system is designed to transport 1 kA of 4.5 MeV electrons with an emittance of 30 millirad-cm. The planar wiggler is provided by a pulsed electromagnet. The interaction region is an oversized rectangular waveguide. Quadrupole fields stabilize the beam in the plane parallel to the wiggler field. The 3 meter long wiggler has a 9.8 cm period. The Free Electron Laser (FEL) will serve as an amplifier for input frequencies of 35 GHz and 140 GHz. The facility is designed to produce better than 500 Megawatts peak power.

The potential for exothermic chemical reactions in waste tanks at Hanford is discussed. Organic chemicals have been added to Hanford waste tanks, particularly as ferrocyanides and when processing sludges at B Plant. Recent planned or ongoing activities involving stored wastes have possibly increased the potential for reaction of these wastes with nitrate salts in the waste tanks. Risk evaluations appear to be deficient in assessing the consequences of a deflagration, and in determining the probability of either a deflagration or detonation. The present question is whether current plans and recent safety-related documentation have given proper consideration to the available information about organic compounds in waste tanks. The principal organic additions to Hanford waste tanks are 1200 tonnes of organic carbon'' and 500 tonnes of Ni{sub 2}Fe(CN){sub 6}. 13 refs.

The kinetic and equilibrium behavior of the Pu + O + H system has been studied by measuring the production of hydrogen gas formed by a sequence of hydrolysis reactions. The kinetic dependence of the Pu + H/sub 2/O reaction on salt concentration and temperature has been defined. The metal is quantitatively converted to a fine black powder which has been identified as plutonium monoxide monohydride, PuOH. Other hydrolysis products formed in aqueous media include a second oxide hydride, Pu/sub 7/O/sub 9/H/sub 3/, and the oxides Pu/sub 2/O/sub 3/, Pu/sub 7/O/sub 12/, Pu/sub 9/O/sub 16/, Pu/sub 10/O/sub 18/, Pu/sub 12/O/sub 22/, and PuO/sub 2/. Thermal decomposition products of PuOH include Pu/sub 2/O/sub 2/H and PuO. A tentative phase diagram for Pu + O + H is presented and structural relationships of the oxide hydrides and oxides are discussed. 10 figures, 5 tables.