A diagram is given of the basic Shiva alignment system. The alignment requirements, as originally specified and as preseently estimated, together with the performance obtained to date from the prototype equipment are described. It is expected that this performance will be satisfactory for even the most alignment-sensitive targets and significantly better than is needed for experiments not requiring highly uniform illumination. The hardware arrangement planned for a typical Shiva chain is shown.

A Class 1 review of the thermal analysis of the LOFT Steam Generator and of the transient thermal analysis of LOFT steam generator thermal well was made to confirm compliance of the analyses with the LOFT Technical Specifications, with the LOFT integral test system - preliminary component design description for the steam generator, and with Appendix C of ANC Specification 60139. Included in this review is an examination of the thermal transients and conditions to insure adequate conservatism in analyzed conditions and transients to which the LOFT Steam Generator (including thermal well) might be exposed while in service at the LOFT reactor facility. Also, a review of the thermal code used was made to check for its applicability to these analyses.

Several experimental routes can be used to develop a better understanding of the polymeric constitution (polyanionic and/or polyhedral distribution) of borate, germanate, and silicate glasses. Spectral, chemical, physical-chemical, and mechanical property information can be determined directly for the glass compositions of interest. Generally, only physical-chemical information is readily accessible for the corresponding high temperature liquids. It will be shown that information on each state of matter has its own particular merits. Most of the evidence thus far published suggests an excellent agreement between polyhedral distributions in an oxide glass and its corresponding high temperature liquid state. There is no well known oxide glass forming system for which such a state of affairs does not exist. In spite of this, occasional efforts are put forth which ignore some of what is known for oxide liquids, glasses, and crystals. Such attempts therefore invariably imply, if only indirectly, that significant changes occur in the polyhedral distributions close to the glass transition temperature region. Specific examples to be discussed will include efforts that avoid well known coordination change equilibria such as BO/sub 3/ reversible BO/sub 4/ and GeO/sub 4/ reversible GeO/sub 6/.

The mechanical structure of the LLL/GA Mirror Hybrid Reactor vessel is briefly discussed. Functional requirements and over-all design considerations leading to selection of a post-tensioned concrete reactor vessel and a modular blanket approach are indicated. Module design life of four years, module replacement, capability and remote fueling are provided by the chosen structural design. (RME)

A waste management strategy for future nuclear fusion power systems is developed using existing regulatory methodology. The first step is the development of a reference fuel cycle. Next, the waste streams from such a facility are identified. Then a waste management system is defined to safely handle and dispose of these wastes. The future regulator must identify the decisions necessary to establish waste management performance criteria. The data base and methodologies necessary to make these decisions must then be developed. Safe management of nuclear fusion wastes is not only a technological challenge, but encompasses significant social, political, and ethical questions as well.

Mechanical design criteria for high-energy neutral beam injectors capable of prolonged operation are examined. The generalized structural, heat transfer, and hydraulics equations are presented for convectively cooled grids. The effectiveness of helium, liquid sodium, and subcooled water for cooling a 2-mm-diameter, 8-m-long grid tube is shown. Cooling effectiveness is determined as a function of the number of tubes in series vs heat flux, where the number of tubes in series ranges from 1 to 100 and the heat flux ranges from 100 to 10,000 W/cm/sup 2/. The stress analysis of the grid tube walls is presented, enabling data to be added to the heat transfer graphs and giving an upper flux limit for some grid materials. Sputtering is found to be a possible limiting factor for the grid lifetimes. In injectors designed for continuous use, long-term operation without excessive maintenance is required and sputtering must be minimized. To accomplish this, several procedures are proposed.

The extraction of information from measured or computed data is all-pervasive; to gain the most value from extracted information, it must often be transformed from one type of data into another, a process that can only preserve or lose information. An information-transformation process based upon Prony's method was found to be increasingly useful for application to electromagnetic-type problems in particular and a growing variety of physical problems in general. This procedure allows the coefficients and exponents (or parameters) of an exponential series to be derived from a sequence of its sampled values. Two basic issues are associated with Prony processing: determination of the status of the input data and application of the procedure as effectively as possible to maximize the information content of the output. The possible uses of the Prony method as an information on-transformation process are discussed; the insight gained from this viewpoint concerning the information content of data is emphasized. Waveform and spectrum characterization, data compression, and inversion of pattern data are considered briefly as applications. 8 figures, 3 tables. (RWR)

Neutral beams, which effectively heat and fuel mirror reactors, provide high-energy particles that readily cross magnetic fields to penetrate, heat, and fuel confined plasmas. The potential reliability, efficiency, and cost of large neutral-beam injectors make them desirable components of an operating mirror reactor. Because neutral beams are a poor source of low-energy particles, some other means of fueling large Tokamaks is needed.

Argus is a twin beam, 20 cm output aperture, Nd:glass laser system that has delivered 4TW to a laser fusion target. This performance is based on the concepts that multiple spatial filtering can prevent beam fill factors. Damage to optics due to self focusing and filamentation does not occur on Argus. The only form of damage is induced by broadband radiation from xenon flashlamps interacting with contaminants on or in the Nd:glass. The severity of damage is measured by the fraction of the beam obscured by the damage sites. This averages 0.1% per surface or 0.75% per arm. The amount of damage does not appear to be strongly related to the number of amplifier firings and generally occurs during the first few firings.

Catalytic Exchange Detritiation: A pilot-scale combined electrolysis catalytic exchange system was constructed. Tritiated Liquid Waste Decontamination (Molecular Excitation): The scavenger and irradiation cell apparatus was completed for the two-photon ISP system. The uv source (xenon flashlamp) was adapted to the photolysis cell. A problem with the optical parametric oscillator was traced to prelasing due to a degradation in isolator rejection, and the laser power supply is being modified. Fixation of Aqueous Tritiated Waste in Polymer Impregnated Concrete: An optimum weight percent of catalyst in the monomer of 0.5 percent and an oven curing temperature of 55/sup 0/C were established. The ratio of monomer to concrete is under investigation. Radiation Chemistry Studies of Tritium Fixation Packages: Pressure increase and gas composition were measured over (1) tritiated water (1000 Ci/l) with and without cement-plaster fixation and (2) tritiated n-octane (1000 Ci/l) with and without vermiculite or absorbal fixation. The back reaction that limits pressure buildup over water was inhibited by the fixative. The pressure buildup over waste vacuum pump oils was much less than the ''worst case'' predicted. Management of High Specific Activity Tritiated Liquid Wastes: Drums of solidified liquid waste were inspected one year after assembly. Of the 96 drums, four …

A calorimeter has been designed for use with the TFTR prototype neutral beam injection system. It consists of three vees each having two 18.8-mm-thick (0.75 in.) copper plates at a 6-deg angle, relative to the beam centerline. The maximum power density on a plate with this arrangement will be 2.0 kW/cm/sup 2/, resulting in a front surface temperature rise of about 420/sup 0/C. A support and retraction system moves the calorimeter in and out of the beam centerline. Various factors used in the selection of the absorber plate material will be discussed and also some experimental test results will be presented.

The PLT or ISX-B ion source has been operated at 40-keV, 60-A, and 0.3-sec pulses with H(D) neutral injected power of 750 kW (approximately 1000 kW) on the PLT device. This report gives a brief description of this system and some future plans. (MOW)

This report is made up of slides presented at the briefing on recommendations for the incorporation of MOPPS-like detail into the BNL/DRI model. Major subjects are: fundamental purpose of energy planning; ERDA planning; hierarchical framework of production functions/models; recommendation; and management plan for implementation of recommendation. (MCW)

This paper describes the design and fabrication of a unique silicon substrate on which gold is sputtered. It produces a finished part and eliminates the need for any etching or other processing. Several different sizes of gold dots and donuts from 50 to 750 microns diameter by 10 microns thick have been made and the process appears to be quite successful.

Based on our current understanding of plasma behavior in mirror reactors, we have recalculated plasma parameters for a fusion engineering research facility (FERF) which uses a magnetic mirror. The most significant changes from results previously reported are a higher value of Q (0.51 vs 0.11) and a higher total neutron rate (2.82 x 10/sup 18/ vs 1.2 x 10/sup 18/ s/sup -1/) yielding a maximum neutron flux of 1.25 x 10/sup 14/ cm/sup -2/ at the wall. The required beam current is approximately 550 A, slightly greater than the 500 A previously estimated.

A device that measures charge-exchange flux to determine the angular distribution of the 2XIIB plasma is described. Charge-exchange products heat circular nickel foils (placed at 15/sup 0/ intervals in theta and at constant radius on an arc parallel to the z-axis) and the voltage drop across the foils (produced by constant-current sources) provides a measure of the changes in resistivity. The charge-exchange flux at each foil is proportional to the plasma distribution at that angle. Use of this technique is limited by the resistivity and heat resistance of the circular nickel foils, but could conceivably be extended to other shapes and materials. The Hall-Simonen and ''time-average'' measurement of angular distribution are compared and the characteristic times of loss (gain) are calculated from theory. The g(..mu..) detector may be used to experimentally verify these times of loss (gain) and also to analyze plasma pressure stability. Current microwave measurements show that plasma has an exponential density dependence in z and assumes a flux tube rather than a p(B) density dependence. A distinct angular distribution (determinable by the detector) is associated with each of these dependencies. The codes to simulate injection and resulting angular distribution, charge-exchange capture, and heating and signal of the …

A glove-box facility was designed to convert plutonium skull metal or unburned oxide to an oxide acceptable for plutonium recovery and purification. A discussion of the operation, safety aspects, and electrical schematics are included.

Recent improvements have made the two-stage, light-gas gun at Lawrence Livermore Laboratory into a dependable source of very energetic planar shocks. Also, the inclined-prism technique has proved useful in observing anomalous behavior of materials, especially at low pressure. The availability of these improved techniques presented an opportunity to re-examine the low pressure, shock-compression characteristics for graphite and, in a search for an additional transformation, to extend some of the data to higher pressures.

A listing is given of Mound Laboratory's sales of stable isotopes of noble gases, carbon, oxygen, nitrogen, chlorine, and sulfur for fiscal years 1976 and 1976A (the period July 1, 1975 through September 30, 1976). Purchasers are listed alphabetically and are divided into domestic and foreign groups. A cross-reference index by location is included for domestic customers. Cross-reference listings by isotope purchased are included for all customers.

Prony's method, a technique for obtaining the parameters of a series of complex exponentials, is used here to analyze the radiation pattern of a linear array of isotropic radiators. The locations and amplitudes of the radiators are derivable from the pattern. Possible applications include imaging and array synthesis. 4 figures, 2 tables.

The central cell of TMX may require hot-ion injection. The resulting velocity-space anisotropy together with the length of the central homogeneous region raise the possibility of convective AIC instability. In this report we demonstrate that the Rosenbluth criterion of less than a thousand-fold amplitude amplification per pass can be satisfied by ion distributions which nevertheless have sufficient anisotropy to be confined within the central cell.

Effective control and monitoring of the Purex aqueous discharges are an extremely important phase of plant operation. Protection of the surrounding environment from radioactive contamination has to be of paramount importance. All possible safety measures need to be utilized and systems in place which provide effective treatment, isolation and monitoring of the discharged streams. Continual evaluation of the discharge systems is necessary to insure effective treatment and control utilizing technically up-to-date methods that will insure minimal contamination release. Presented herein is an evaluation of Purex aqueous discharge treatment, control and monitoring capabilities and comparison with ERDA Manual Chapter 0511, 0513 and 0524 requirements. Where applicable, recommendations are submitted to accomplish those requirements.

This report describes the non-LTE atomic-state computer program, XSNQ-U. The original classified report was issued in 1971. Since then, important changes and improvements have been included. XSNQ-U provides frequency-dependent emission and absorption coefficients for a material not in LTE (local thermodynamic equilibrium). As in XSNB, an LTE opacity subroutine, a compromise was sought between accuracy and computer speed. The result, XSNQ-U, is intended for use as a subroutine in any transport code. This report surveys the basic non-LTE equations for the average ion model, as pioneered by Grasberger (UCRL-12408 and -5135), and gives details for the approximations and technique used in XSNQ-U. Also included are some illustrative numerical examples. Since the writing of the classified report, the code has been modified to handle the case of multiple elements. The extension is straight forward; the notation of this report would only be more cumbersome if the single-element notation were replaced by the multiple-element notation. Also, the method of solving the rate equations by using analytical differentials as discussed in the classified report was replaced by a more direct incremental differences scheme, which is discussed in the present version. 12 figures, 2 tables.

A brief description is presented of the physical processes, models and numerical methods employed in the LASNEX code for calculating inertial confinement fusion.