A gas chromatographic determination of dibutylbutyl-phosphonate in the presence of tributylphosphate was developed. The separation was done on a 183 cm by 3 mm stainless steel column packed with 10 percent Carbowax 20M--TPA on 80/100 mesh Chromosorb W AW and detected by flame ionization. A nitrogen carrier gas flow of 40 cm/sup 3//min and an oven temperature of 180/sup 0/C produced optimum resolution and column efficiency. The use of temperature programming reduced retention times and thus analysis time. An internal standard of 10 percent v/v n-tridecane was added to all samples and standards.

Calculations have been performed to determine the limiting concentration of plutonium required for criticality when added to normal uranium. The bias of the method has been evaluated by comparing the calculated and experimental limiting /sup 235/U enrichments for criticality of oxide-water mixtures and of nitrate-water mixtures.

The model fuel plant is based on the proposed Westinghouse Anderson, S.C., plant and is typical of plants that will be constructed and operated in 1980 to 1990. A number of plant systems and procedures are uncertain, and in these cases judgment was used in describing relevant parameters in order to provide a complete model on which to design an inspection plan. The model plant does not, therefore, strictly represent any planned facility nor does it strictly represent the ideas of Westinghouse on plant design and material accountability. This report is divided into two sections. The first section is the IAEA Design Information Questionnaire form that contains an outline of all information requested. The second section is a complete listing of design information. (DLC)

The pipe rupture study is designed to extend the understanding of failure-causing mechanisms and to provide improved capability for evaluating reactor piping systems to minimize the probability of failures. Following a detailed review to determine the effort most needed to improve nuclear system piping (Phase I), analytical and experimental efforts (Phase II) were started in 1965. This progress report summarizes the recent accomplishments of a broad program in (a) basic fatigue crack growth rate studies focused on LWR primary piping materials in a simulated BWR primary coolant environment, and (b) studies directed at quantifying weld sensitization in Type-304 stainless steel.

Conclusions on the magnitude of the inspection effort and its effectiveness in meeting IAEA objectives are summarized: the minimum goal quantity that can be detected with 95 percent probability is 6 kg Pu. eight to nine resident inspectors are necessary to monitor all operations (3 shifts a day) and to perform verification measurements (23 per day). The facility must also perform inventories monthly if the goal of 6.0 kg is to be attained. Bi-monthly inventory and continual on-site resident inspection can achieve a detection goal quantity of 8.0 kg Pu with 95 percent detection probability. For annual inventories, the detection goal quantity for a 95 percent detection probability is 40 kg Pu. The probability for detecting 8 kg is less than 20 percent. The total inspection effort for a 200 MT/year RFP is estimated to exceed 15 man-years if IAEA headquarters support and analytical laboratory time are added to on-site manpower requirements. Surveillance and containment in the form of seals must be applied to prevent double inventorying and to assure that samples are extracted from the vessel or container being measured. These assurances will probably be achieved by on-line instrumentation installed by the IAEA prior to plant start-up. For assessment, …

A code module, STEEP4, is developed to calculate the fusion reaction rates in terms of the specific reactivity (sigma v) which is the product of cross section and relative velocity averaged over the actual ion distributions of the interacting particles in the plasma. The module is structured in a way suitable for incorporation in thermonuclear burn codes to provide rapid and yet relatively accurate on-line computation of (sigma v) as a function of plasma parameters. Ion distributions are modified to include slowing-down contributions which are characterized in terms of plasma parameters. Rapid and accurate algorithms are used for integrating (sigma v) from cross sections and spectra. The main program solves for (sigma v) by the method of steepest descent. However, options are provided to use Gauss-Hermite and dense trapezoidal quadrature integration techniques. Options are also provided for rapid calculation of screening effects on specific reaction rates. Although such effects are not significant in cases of plasmas of laboratory interest, the options are included to increase the range of applicability of the code. Gamow penetration form, log-log interpolation, and cubic interpolation routines are included to provide the interpolated values of cross sections.

The uranium-2 wt percent molybdenum alloy was prepared, processed, and age hardened to meet a minimum 930-MPa yield strength (0.2 percent) with a minimum of 10 percent elongation. These mechanical properties were obtained with a carbon level up to 300 ppM in the alloy. The tensile-test ductility is lowered by the humidity of the laboratory atmosphere. (auth)

Progress is reported in the areas of sodium jet dispersed tests, SOMIX code development, iodine attenuation tests, aerosol leakage tests, characterization of aerosols from vaporized fuel, and high-temperature properties of fuel materials.

A description is given of design considerations, physical layout, electronics, and PDP-11 computer programming for the Energetic Pion Channel and Spectrometer (EPICS) taut-wire system. EPICS is a high-resolution pion channel and spectrometer facility at Los Alamos Meson Physics Facility (LAMPF). The taut-wires are remote, position-sensing devices attached to the relatively inaccessible channel magnets for monitoring their relative positions.

An elementary description is given of the basic vocabulary and concepts associated with finite difference modeling. The material discussed is biased toward the types of large computer programs used at the Lawrence Livermore Laboratory. Particular attention is focused on truncation error and how it can be affected by zoning patterns. The principle of convergence is discussed, and convergence as a tool for improving calculational accuracy and efficiency is emphasized.

Tokamak discharges are characterized by electron densities usually approximately 0.3 to 1.0 x 10/sup 14/ cm/sup -3/ and temperatures from a few hundred eV to several keV. In addition to the working gas (H or He), the plasma normally contains some light impurities (approximately 10/sup 12/ cm/sup -3/ O or C) that are completely stripped except at the outer periphery, and heavier elements from the vacuum wall and current-aperture limiter (Fe, Cr, Ni, W, Mo and others, approximately 10/sup 10/-10/sup 11/ cm/sup -3/) that remain partly stripped, hence relatively strongly radiating, throughout the discharge. Other elements, especially noble gases, may be deliberately added for diagnostic purposes. Resonance lines of Fe and Ar in the beryllium and lithium sequences, of Fe, Kr, and Mo in the magnesium and sodium sequences, and of Mo and Xe in the zinc and copper sequences have been used for rough determination of plasma composition. Since crucial plasma characteristics such as temperature and confinement time are sensitively affected by the local composition, it is essential to improve the available atomic data necessary for more accurate analysis: wavelengths, transition probabilities, excitation, ionization and recombination rates, especially for the heavier elements.

Deluging of air-cooled heat exchangers with water during warm periods holds the promise of increasing heat rejection capability and reducing the cost of dry cooling. One of the principal uncertainties in the use of the deluge concept is the tendency toward deposition of solids from the delugate. Small amounts of calcium carbonate scale may significantly reduce the cooling efficiency of a deluged system by reducing the heat transfer coefficient and interfering with delugate flow. Thus the question of delugate water quality is of major importance in evaluating scale formation and its effect on heat transfer in the deluged dry cooling system. The paper discusses, in relation to the deluged dry cooling system, the importance of scale prevention, the theory of scale formation and application of this theory to the deluged system, the problems of delugate evaporation, and delugate treatment required to prevent scaling.

None

Premature failures during proof testing of pressurized-gas-metal-arc (PGMA) welded beryllium assemblies were investigated. The failures were almost entirely within the beryllium (a forming grade, similar to HP-10 or S-240), close to and parallel to the weld interface. The aluminum-silicon weld filler metal deposit was not centered in the weld groove in the failed assemblies, and failure occurred on the side of the weld opposite the bias in the weld deposit. Tensile tests of welded samples demonstrated that the failures were unrelated to residual machining damage from cutting the weld groove, and indicated small lack-of-fusion areas near the weld start to be the most likely origin of the failures. Acoustic emission was monitored during tensile tests of the welds. The majority of acoustic emission was probably from crack propagation through the weld filler metal. Tensile bars cut from the region of the weld start behaved differently; they failed at lower loads and exhibited an acoustic emission behavior believed to be from cracking in the weld metal-beryllium interface. Improvement in the quality of these and similar beryllium welds can therefore most likely be made by centering the weld deposit and reducing the size of the weld start defect. 21 fig.

None

Research on theoretical high energy physics is summarized. A list of publications is included. (JFP)

Effects of nuclear elastic scattering and large angle ion-ion Coulomb interactions causing large energy transfers from energetic ions slowing down in plasmas to the plasma ions are examined. The effects examined are the fusion probability, the slowing down time, and the fraction of the ion energy imparted to the plasma ions and electrons. A new multigroup method for the solution of the ion slowing-down equation that can accurately take into account large energy transfer reactions is described.

A quality-assurance program for tritium-handling systems at the Lawrence Livermore Laboratory tritium facility has been developed. Operational guidelines governing system design, construction, and testing have been written. A certified-material storeroom has been established to procure and distribute high-quality materials. Ten systems are currently being modified under the new guidelines.

The effect of impurities on low frequency drift modes of a toroidally-confined plasma is investigated by the gyro-kinetic equation. It is assumed that electrons are in the banana regime and ions in the plateau regime. Impurity collision damping is found to be significant in the usual trapped electron mode. A new instability due to the impurities can occur for normal profiles and impurities peaked at the center. Quasi-linear considerations show that impurities will be driven outward if such an instability occurs.

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives. (JGB)

High-purity carbonaceous material can be effectively analyzed for small quantities of volatile matter by heating the sample to 950/sup 0/ C in a quartz reaction tube under a flow of an inert gas. All of the operations of the analysis were performed at the exit end of the reaction tube. The volatile matter measured by weight loss of the sample confirmed its reproducibility in this type of analysis. (auth)

Separate abstracts were prepared for each of the data-containing sections of this report. Additional sections deal with publications, titles of papers presented at scientific and technical meetings, personnel, etc. (RWR)

The continuous-point-source computer code calculates concentrations and surface deposition of radioactive and chemical pollutants at distances from 0.1 to 100 km, assuming a Gaussian plume. The basic input is atmospheric stability category and wind speed, but a number of refinements are also included.

Volume V of the five-volume report consists of appendices, which provide supplementary information, with emphasis on characteristics of geologic formations that might be used for final storage or disposal. Appendix titles are: selected glossary; conversion factors; geologic isolation, including, (a) site selection factors for repositories of wastes in geologic media, (b) rock types--geologic occurrence, (c) glossary of geohydrologic terms, and (d) 217 references; the ocean floor; and, government regulations pertaining to the management of radioactive materials. (JGB)