The Containment Systems Test Facility (CSTF) provides the capability of performing large-scale aerosol behavior experiments at a scale factor of approximately 0.5 in height for a typical reactor containment building. The containment height is 20.3 m, the volume is 850 m/sup 3/, the design pressure is 5 bar, and quantities of sodium up to 1250 kg can be sprayed or spilled for sodium combustion product aerosol sources. Instrumentation is provided for characterization of the aerosol and the containment atmosphere. This paper describes the aerosol sampling techniques and instruments used in the CSTF and discusses their accuracy and reproducibility.

A brief review of the photon-gluon fusion model for heavy quark (virtual) photoproduction is presented. It is compared with existing data, and some difficulties and speculations are discussed. 12 figures.

The application of computer codes and mathematical models to the solution of problems concerning power reactor core kinetics is discussed.

The basic purpose of T3C activity is to show how to acquire specific corrosion cost information so that overall costs for doing business can be reduced. The scope of T3C is to accumulate data, appraise methods, develop recommended practices, promote knowledge and communicate relative to the economic evaluation of corrosion and counter corrosion techniques.

Neutron yields, from interactions of multiampere 40- to 120-keV deuterium beams with deuterium atoms implanted in copper targets, have been measured in order to provide input data for shielding of neutral-deuterium beam facilities for magnetic fusion experiments.

The objective of this research is to assess the sensitivity of design parameters for a community solar heating system having annual thermal energy storage to factors including climate, building type, community size, and collector type and inclination. The system under consideration uses a large, water-filled, concrete-constructed tank for providing space heating, and domestic hot water (DHW). Collector field area and storage volume have been sized for 440 community designs in 10 geographic locations. Analysis of the data has allowed identification of those parameters that have first order effects on component sizing. Two linear relationships were derived which allow system sizing. The average ambient temperature is used to determine average yearly collector efficiency. This parameter combined with estimates of space/DHW loads, storage/distribution losses, and total yearly insolation per square meter allows estimation of collector area. Storage size can be estimated from the winter net load which is based on space and DHW loads, storage/distribution losses, and collector solar heat for the winter months. (MHR)

Superconducting magnets will play an important role in fusion research in years to come. The magnets which are currently proposed for fusion research use the concept of cryostability to insure stable operation of the superconducting coils. This paper proposes the use of adiabatically stable high current density superconducting coils in some types of fusion devices. The advantages of this approach are much lower system cold mass, enhanced cryogenic safety, increased access to the plasma and lower cost. (MOW)

Testing of TFTR neutral beam (NB) sources has begun at the LBL Neutral Beam System Test Facility (NBSTF). Operation at 120 kV, 65 A, 0.5 sec should be achieved soon. Because NB sources spark down frequently during conditioning, the main accelerating (accel) power supply must be interrupted within a few microseconds to avoid degrading the voltage holding capability, or even the damaging, of the NB source. A variety of improper magnitudes and/or ratios of voltages, currents, and times can occur and must be recognized as fault conditions in order to initiate a prompt interruption of the accel power supply. This paper discusses in detail the key signals which must be monitored and the manner in which they are processed in fault detector circuitry for safe operation of LBL NB sources. The paper also reviews the more standard interlocks and protective features recommended for these sources.

The evolution of the Doublet III neutral beam armor is followed from the initial design of a radiation cooled metallic tile to the present actively cooled graphite design. Results of the thermal and stress analyses that dictated the present design are reviewed.

This paper describes the Doublet III Vacuum Control System in which all input signals and output loads are connected to a programmable controller (PC) for logical interfacing. Input signals derived from CAMAC, control panels, limit switches, etc., are implemented as output signals to CAMAC, vacuum valves, pump motors, etc., according to a logic program stored in the PC memory. The memory can be easily programmed by anyone familar with either Boolean algebra or relay-ladder network diagrams. The program data is entered with the aid of a calculator like, keyboard instrument with LED readout displays. The PC system contains a 1024 word RAM memory with a battery backup system to provide 72 hours protection of contents in case of power failure. (MOW)

An integrated system for quality status and inventory tracking of Fast Flux Test Facility (FFTF) driver fuel pins has been developed. Automated fuel pin identification systems, a distributed computer network, and a data base are used to implement the tracking system.

Basic parameters for the beamline are for the injection of 20 MW of 120 kV neutral deuterium atoms from 3 sources per beamline with a pulse rate of 0.5 seconds every 300 seconds. At LBL, a complete test facility consisting of a shielded enclosure, control room, computer facilities, power supplies, cryogenics supply system, external vacuum pumping system as well as the other conventional auxiliaries allows for prototypical operation of the beamline. This paper presents the various facets of the task of bringing such a prototype through design, procurement, fabrication and construction to operations.

A total of 55,000 m of multifilamentary Nb-Ti superconductor in minimum lengths of 380 m are required for the Mirror Fusion Test Facility. This conductor is a large cross-section monolith and, as such, has presented several new manufacturing challenges. In addition, a monolith requires more stringent quality assurance procedures than braids or cables. This paper describes the manufacturing steps and the quality assurance program which have been developed for the MFTF superconductor core.

Material vacuum properties played an important part in designing the Neutral Beam Injector System for General Atomic's Doublet III Tokamak. Low operating vacuum tank pressures were desired to keep re-ionization of the Neutral Beam to a minimum. Plasma contamination was also a major concern, hence stringent material impurity constraints were imposed. Outgassing Rate Measurement and Residual Gas Analyses were performed on different types of materials to determine if their vacuum properties were compatible with the Neutral Beam Injector System requirements.

Comparisons were made between predicted and measured thermomechanical displacements and stresses for in situ heating experiments at a depth of 340 m in a granite body at Stripa, Sweden. We found that taking into account the temperature dependence of the thermal expansion coefficient and the mechanical properties of the rock substantially improves the agreement between theory and experiment. In general, the displacements calculated using laboratory values of rock properties agree better with field data than in the case of stresses. This may be due to the difference between in situ and laboratory rock modulus. The significance of temperature-dependent rock properties and strength to thermomechanical failure is also discussed.

An extensive experimental study of the degradation of existing forms of defense-related, transuranic-contaminated (TRU) wastes is being conducted by and for Sandia Laboratories. Studies have been performed under environmental conditions expected for deep geologic isolation in the Waste Isolation Pilot Plant (WIPP), a bedded-salt TRU waste repository planned for southeastern New Mexico. A primary purpose of this program has been to support the US Department of Energy in establishing waste acceptance criteria for TRU wastes for isolation in the WIPP. TRU waste forms investigated include cellulosics (paper, rags, wood), plastics, rubbers, mixed organic composite, bitumen, a developmental concrete-TRU ash matrix, mild steel, and inorganic process sludges. This review includes laboratory and field results for waste degradation under a range of conditions, resultant gas generation rates, gas compositions, corrosion rates, and microbial formation and degradation of chelating agents.

Combining the modern and proven power conversion system of the closed-cycle gas turbine (CCGT) with an advanced high-temperature gas-cooled reactor (HTGR) results in a power plant well suited to projected utility needs into the 21st century. The gas turbine HTGR (HTGR-GT) power plant benefits are consistent with national energy goals, and the high power conversion efficiency potential satisfies increasingly important resource conservation demands. Established technology bases for the HTGR-GT are outlined, together with the extensive design and development program necessary to commercialize the nuclear CCGT plant for utility service in the 1990s. This paper outlines the most recent design studies by General Atomic for a dry-cooled commercial plant of 800 to 1200 MW(e) power, based on both non-intercooled and intercooled cycles, and discusses various primary system aspects. Details are given of the reactor turbine system (RTS) and on integrating the major power conversion components in the prestressed concrete reactor vessel.

The purpose of the work is to develop a new type of solar thermal receiver that utilizes a dispersion of very small particles suspended in a gas to absorb the radiant energy from concentrated sunlight. The Small Particle Heat Exchange Receiver (SPHER) operates by injecting a very small mass of fine, light-absorbing particles into the gas stream. The gas-particle mixture then enters a transparent heating chamber into which the concentrated solar flux is directed. The particles absorb the radiation and because of their very large surface area, quickly transfer the heat to the surrounding gas. The gas-particle mixture continues to heat until the particles oxidize or vaporize. The gas may be heated to medium or high temperatures as suitable for a variety of industrial process heat or thermal power requirements. In particular it can be used as a high efficiency receiver to supply hot air or gas to operate a chemical or fuel production process. Research progress is summarized. (WHK)

Recent results rom the Mark II Detector at SPEAR are presented. These include measurements of the decays tau/sup -/ ..-->.. rho/sup -/..nu../sub tau/ and tau/sup -/ ..-->.. K*/sup -/(890)..nu../sub tau/, observation of direct photons at the psi, inclusive proton and ..lambda.. production and measurements of charmed baryon and charmed meson decays.

This paper describes the diagnostic data acquisition, processing and archiving computer system for the Doublet III fusion research device. This paper's emphasis is mainly on the software, but provides a description of the hardware configuration. (MOW)

Methods to determine resin characteristics, i.e., cesium equilibria and diffusion rates, were developed. These parameters can now guide resin selection and aid in interpreting column performance. The K/sub D/ cesium ion concentration relation gives evidence of three different types of ion exchange sites. The countercurrent load/elution/regeneration cycle for the removal of cesium by ion exchange repeatedly reached the goal decontamination factor (DF) of 10,000 at throughputs up to 60 column volumes. Resin backwashing appears feasible, but further development of column geometry will be required. The proposed ammonium elutriant is satisfactory. Regeneration end-point can be controlled by electrical conductivity monitoring.

Generation of electric power from inertial confinement fusion requires a reaction chamber. One promising type, the High Yield Lithium Injection Fusion Energy (HYLIFE) chamber, includes a falling array of liquid lithium jets. These jets act as: (1) a renewable first wall and blanket to shield metal components from x-ray and neutron exposure, (2) a tritium breeder to replace tritium burned during the fusion process, and (3) an absorber and transfer medium for fusion energy. Over 90% of the energy produced in the reaction chamber is absorbed in the lithium jet fall. Design aspects are included.

Measurements have been made of the total backscattered D/sup -/ and H/sup -/ yields from Cs, Rb, K, Na and Li surfaces bombarded with D/sub 2//sup +/, D/sub 3//sup +/, H/sub 2//sup +/ and H/sub 3//sup +/ in the energy range 0.15 to 4 keV/nucleus. All measurements were made at a background pressure less than 10/sup -9/ Torr and the alkali-metal surfaces were evaporated onto a substrate in situ to minimize contamination of surfaces. For each target, the D/sup -/ and H/sup -/ yields exhibited maxima (as high as 8% per incident deuteron or proton for Cs); the maxima occurred at incident energies between 300 and 1000 eV/nucleus and always occurred at a lower incident energy for H than for D for a given target. Both the H/sup -/ and D/sup -/ yields decreased, at any measured energy, in going from Cs to Li in the order given above. Measurements of the H/sup -/ yield were also made for H/sub 3//sup +/ bombarding a W substrate, as a function of the work function of the target, as Li was deposited on the W. The work function of the target showed a minimum as the Li coverage was increased and the …

Recent development efforts on 120-keV ion sources for neutral-beam systems for the fusion program have focused on producing pulse-lengths longer than the 0.5-sec originally specified for TFTR and improvement of the atomic-ion fraction of the beam. From heat-load measurements of the accelerator grids we deduce that our edge cooled grids should be capable of operation for pulse lengths of the order of 2 seconds; we have operated our 8- x 10-cm accelerator for 1.5-seconds and have fabricated a water-cooled accelerator for longer pulse operation. A multi-cusp ion source has been used to produce 65A beams with D/sup +/ fractions of about 75%.