The effect of microstructure of two phase alloys, consisting of a softer, ductile matrix and a harder interspersed phase, on erosion behavior was determined. The stress and strain distribution in a two phase alloy where the second, hard phase is a distribution of particles in a more ductile matrix was calculated. It was determined that a spheroidized 1075 carbon steel eroded 30 percent less than a pearlitic microstructure of the same steel even though the spherodized form was 21 R/sub B/ points of hardness lower than that of the pearlitic steel. The computerized calculation of stresses and strains from the impact of eroding particles on a two phase alloy surface were used to define the ability of the particle impact to induce voids and cracks in the target material that could cause material loss. The resultant predicted voids and cracks were related to experimentally determined behavior of spherodized steel.

Transuranium elements have been introduced to the environment by a variety of ways including fallout from weapons testing, leakage from nuclear power reactors, waste effluent from nuclear fuel processing and leakage of radioactive waste from ocean dump sites. Several methods of curium detection and analysis in samples from marine ecosystems are contrasted and discussed in this paper.

The potential radiological impact of the siting of 20 light-water reactors and associated nuclear fuel cycle facilities on the Hanford reservation was evaluated by calculating the potential radiation doses received by individuals and populations in the vicinity of the reservation. The largest contributor to the potential radiation doses, to both the individual and the 50-mile population, were the effluents from the conceptual 1500 MT/yr fuel reprocessing plant. The effluents from the 20 reactors combined was the second largest contributor. The radiation dose contributions from the 300 MT/yr mixed oxide fuel fabrication plant were insignificant. The highest organ dose from all facilities combined was 24 mrem/yr to the child thyroid; followed by 8 mrem/yr to the adult thyroid. The 50-year collective dose commitment to the population within 50 miles was about 50 man-rem for most organs of reference, while the estimate for bone was 70 man-rem. With the exception of /sup 85/Kr, the release rates of radionuclides were within the EPA guidelines. Removal of about 90% of the 4 x 10/sup 5/ Ci/yr per gigawatt-year of electricity of /sup 85/Kr from the fuel reprocessing plant gaseous effluents would be required for compliance with the EPA guidelines.

Deep Level Transient Spectroscopy (DLTS) has been applied for the first time to high-purity germanium p-i-n diodes. Using the correlator technique, a large number of peaks due to acceptor levels in the forbidden band have been observed. The levels due to substitutional copper, to copper--hydrogen complexes and to divacancy-hydrogen defects have been positively identified. Several unknown levels have been discovered. The results obtained with DLTS are in excellent agreement with results from Hall-effect measurements. DLTS is the perfect tool to follow the creation and annealing of radiation defects.

An extractor for accelerating 50 A of deuterium ions to 10 keV for injection into a metal-vapor charge-exchange cell has been designed. The beam-forming electrodes are convection cooled and capable of continuous service.

In work for the United States Nuclear Regulatory Commission, Lawrence Livermore Laboratory is developing an assessment procedure to evaluate the effectiveness of a potential nuclear facility licensee's material control (MC) system. The purpose of an MC system is to prevent the theft of special nuclear material such as plutonium and highly enriched uranium. The key in the assessment procedure is the generation and analysis of the adversary event sets by a directed graph and fault-tree methodology.

Double-shelled inertial confinement fusion targets in which the outer shell is exploded have been studied with LASNEX. To achieve high DT density, configurations have been found in which the inner shell is ablatively driven by the hot outer shell. Calculations indicate that greater than 100 times liquid DT density can be achieved with the Shiva laser while still retaining some of the symmetry and stability advantages of the single-shelled exploding pusher target. The relative merits of transferring energy to the inner shell by electron conduction and by hydrodynamic work will be discussed.

In accordance with the US--USSR Cooperative Program in MHD joint US--USSR tests were conducted in May 1978 at the U-02 facility of an MHD generator section consisting of U.S.-built electrode blocks and USSR-built insulating walls. The main purpose of the experiment was to conduct continuous 100-hour duration tests of materials and structures of electrode blocks; in particular, to study the behavior of ceramic electrodes and insulators in operating conditions of an MHD generator, the electro-physical and thermal characteristics of the working section as a whole and electrodes in particular, and to analyze the change in the phase composition and structure of materials during the test. The main thrust of the experiment was a study of electrode material behavior. Six varieties of electrodes based on doped lanthanum chromite were tested and investigated. The electrodes were made of fine grained, hot-pressed mass (the porosity of the ceramic was 2 to 3%). The interelectrode insulators were made of magnesial and magnesial-spinel ceramic also manufactured by the hot pressing method. Results are presented and discussed.

The status of negative ion based neutral beam systems is reviewed. Methods of generating the negative ions of the hydrogen isotopes and the handling and acceleration of these ions are considered. The status of plans for stripping the ions and for constructing beam systems are included.

Since the inception of the hypothesized transition phase, for the late stages of a postulated LMFBR accident, there has been a continual effort to characterize the anticipated conditions of such a hypothetical state. To date, several techniques and methods have been employed to analyze the potential for energetic criticality. As part of this effort, an arbitrary criterian of monotonical dispersiveness has been employed as the measure of diminished recriticality potential. The various attempts to demonstrate monotonic dispersiveness have included experimental demonstrations, theoretical approaches, and integrated analysis using both. As part of this treatment, flow regime maps have been devised as a convenient method for inferring the state of dispersiveness. They included bubbly, churn turbulent, foam and drop fluidized regimes. Of these, foam and drop fluidized regimes were considered the most dispersive. The main thrust of the analysis to date, including flow regime maps, relates primarily to the open pool configuration. However, the bottled configuration may be the pertinent geometry. To date, no reliable escape path has been demonstrated for the advanced stages of core disruption, although strong potential escape mechanisms have been identified and are currently being analyzed. The bottled pool is examined in this paper.

The sodium fire test program and related studies at the Hanford Engineering Development Laboratory (HEDL) are described. The program is analytical and experimental in scope, with computer code development and experimental verification. Tests have ranged in size from gram quantity laboratory tests to 1600-kg sodium spills. The experimental work is performed in two facilities: the Large Sodium Fire Facility (LSFF) and the Containment Systems Test Facility (CSTF). Sodium fire extinguishment tests which verified the Fast Flux Test Facility (FFTF) secondary sodium fire protection system are described and related informaion on sodium burning rates and smoke release rates are correlated. The burning rates are compared to theoretical predictions based on heat and mass transfer analogy, with good agreement. Comparisons with the SOFIRE-II code are also made. Sodium combustion aerosol properties are defined as to chemical and physical nature, settling in closed vessels and effect of added water vapor. The HAA-3B aerosol behavior computer code is compared to tests in the 850-m/sup 3/ CSTF containment vessel. Sodium spray tests in the CSTF are compared with the SPRAY computer code. An air cleaning program is described, which has the objective of removing high mass concentration sodium combustion aerosols from vented cells and containment …

Parity nonconservation was observed in the inelastic scattering of longitudinally polarized electrons from an unpolarized deuterium target at 19.4 and 22.2 GeV. An asymmetry A = (sigma/sub R/ - sigma/sub L)/(sigma/sub R/ + sigma/sub L/) = (-9.5 +- 1.6) x 10/sup -5/ Q/sup 2/, Q/sup 2/ in (GeV/c)/sup 2/ was found for values of Q/sup 2/ near 1.4. The statistical and systematic errors are each about 9 percent of the measured asymmetry. This result is consistent with predictions from the standard Weinberg--Salam SU(2) x U(1) model. Using the simple quark-parton model of the nucleon, the value sin /sup 2/theta/sub W/ = 0.20 +- 0.03 is obtained. 21 references.

Results are presented from the steady state fuel irradiation program in EBR-II, which is intended to provide the technology and engineering test data in near-term support of the design and operation of the Fast Flux Test Facility (FFTF) and Fast Breeder Reactors (FBR's) utilizing the reference fuel system - UO/sub 2/--PuO/sub 2/ mixed oxide with 25 +- 5 w/o PuO/sub 2/ and 20% CW Type 316 stainless steel cladding. This program is also intended to develop the base for longer term innovative improvements and design changes required for FBR's and develop design criteria and associated computer-based design codes for accurately predicting fuel performance.

A brief description is given of the parameters of electron-positron colliding beam machine effort now going on, and the experiments planned for machine turn-on or soon thereafter.

Two high-purity germanium coaxial detectors, having opposite electrode configurations from one another, but fabricated from the same germanium crystal, were irradiated simultaneously with fast neutrons from an unmoderated /sup 252/Cf source. Both detectors were 42 mm diam. The detector having the conventional electrode configuration was about 28 times more sensitive to radiaion damage than was the detector havng the p/sup +/ contact on the coaxial periphery. These results prove that germanium coaxial detectors having the conventional electrode configuration should not be used in any situation subject to significant radiaiton damage. This conslusion was anticipated because the defects produced by neutron and proton irradiaiton of germanium act predominantly as hole traps.

In order to be economically viable, sodium-cooled reactors must operate at fairly high temperatures (500/sup 0/C) and with long, uninterrupted fuel cycles. These conditions increase the potential for radioactive corrosion product transport; achieving the goal of long uninterrupted fuel cycles means that release and transport of fission products from breached fuel pins will undoubtedly have to be controlled. This ppaper shows that control of radioactive material transport is an achievable goal.

This report presents details of the study design and methods for a retrospective epidemiological study on the health effects, if any, of stationary and alternating magnetic fields produced by man-made devices such as cyclotrons, controlled thermonuclear reactors (CTR), high voltage-high current transmission lines, magnetohydrodynamic devices (MHD), energy storage systems, and isotope separation facilities. The magnetic fields to which the workers can be exposed are as high as 10,000 gauss and the anticipated increase in magnetic fields associated with the environment and transmission lines near these devices is a few times the natural earth magnetic field. Thus the objectives include acquisition of low exposure data which can be used to evaluate any risks to the population incidentally exposed to environmental increases in magnetic fields, as well as an acquisition of high exposure data to be used in determining allowable exposure standards for the technical personnel working at CTR and MHD facilities. From the present status of knowledge on biological effects of magnetic fields, it is not possible to extrapolate or rationally conclude maximum permissible exposure levels for magnetic device workers and the population at large. There are no known previous studies of the effects of long-term exposure to magnetic fields involving …

The growing acceptance of containment and surveillance as a means to increase safeguards effectiveness has provided impetus to the development of improved surveillance and containment devices. Five recently developed devices are described. The devices include one photographic and two television surveillance systems and two high security seals that can be verified while installed.

A test drift chamber has been constructed with a segmented cathode for measuring the second coordinate. A corona discharge source has also been constructed to measure the response of the cathode segments. Various size segments were studied and the position resolution and pulse height distributions measured.

A synthesis and preliminary interpretation of predominantly geophysical information relating to the Klamath Basin geothermal resource is presented. The Swan Lake Valley area, northeast of Klamath Falls, and the Klamath Hills area, south of Klamath Falls, are discussed in detail. Available geophysical data, including gravity, magnetic, electrical resistivity, microseismic, roving dipole resistivity, audio-magnetotelluric (AMT) and magnetotelluric (MT) data sets, are examined and reinterpreted for these areas. One- and two-dimensional modeling techniques are applied, and general agreement among overlapping data sets is achieved. The MT method appears well suited to this type of exploration, although interpretation is difficult in the complex geology. Roving dipole and AMT are useful in reconnaissance, while gravity and magnetics help in defining structure. For the Swan Lake Valley the data suggest buried electrically conductive zones beneath Meadow Lake Valley and Swan Lake, connected by a conductive layer at 1 kilometer depth. In the Klamath Hills area, the data suggest a conductive zone centered near the northwestern tip of Stukel Mountain, associated with a concealed northeast-trending cross-fault. Another conductive zone appears near some producing hot wells at the southwestern edge of the Klamath Hills. These conductive zones may represent geothermal reservoirs. Specific types of follow-up work are …

A high yield lithium injection fusion energy chamber is described which can conceptually be operated with pulsed yields of several thousand megajoules a few times a second, using less than one percent of the gross thermal power to circulate the lithium. The concept is suitable for either lasers or heavy ion beams propagating in background gases. Because a one meter thick blanket of lithium protects the structure, no first wall replacement is envisioned for the life of the power plant. The induced radioactivity is reduced by an order of magnitude over solid blanket concepts. The design calls for the use of common ferritic steels and a power density approaching that of a LWR, promising shortened development times over other fusion concepts and reactor vessel costs comparable to a LMFBR.

Using a DEC LSI-11 microprocessor, a thermoluminescence dosimetry reader for personnel dosimetry has been developed. This microprocessor provides system control, accumulates data for temporary storage on a cassette, and later outputs the data to a large computer. The microprocessor also provides a human/system interface through a computer terminal. A programmable high-voltage supply and a light-emitting diode are used in the reader system to automatically control photomultiplier tube gain.

A brief FFTF project description is provided which includes general plant siting information, general layout, plant design parameters, description of principal systems and components, and description of support facilities. The current status of the FFTF project is provided, including status of plant construction, overall status of the plant checkout and test program, status of operating authorization and plant operating procedures and personnel, and status of reactor core components and experiments. Specific information on the acceptance test program and early program results is discussed. The role of FFTF in the future breeder program is described, including its objectives for verification of plant system and components designs and operability and use as an irradiation test facility.

A ten channel filter-fluorescer spectrometer was designed for measuring x-ray spectra from 2 to 115 keV at the Argus and Shiva laser facilities. Previously x-ray spectra were measured with filtered detectors; however, the higher fluxes and more complicated spectra observed in recent experiments requires the greater photon energy definition of this technique. Five filter-detector channels are also incorporated in the spectrometer for measuring low intensity sources. Five Pb-filtered detectors will be used for obtaining spectral information for energies greater than 100 keV. Provisions are being made to automate this diagnostic to produce the x ray spectrum minutes after shot time.