JAI examined alternative methods for structuring charges for federal interim storage (FIS) services and concluded that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, (4) impact aid payments made in accordance with Section 136(e) of the Act, and (5) module costs (i.e., storage casks, drywells or silos). The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under- or over-estimation in the costs used to calculate the Initial Payment of the fee (including savings due to rod consolidation), and (2) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management …

Construction and evaluation of salmonid habitat improvements on Fish Creek, a tributary of the upper Clackamas River, is designed to increase the annual number of chinook and coho salmon, and steelhead trout smolt outmigrants. The primary objectives of the evaluation include the: (1) evaluation and quantification of changes in salmonid spawning and rearing habitat resulting from a variety of habitat improvements; (2) evaluation and quantification of changes in fish populations and biomass resulting from habitat improvements; and (3) evaluation of the cost-effectiveness of habitat improvements developed with BPA and Forest Service funds on Fish Creek. This report focuses on the projects completed in the basin in 1983, 1984, and 1985, and their evaluation.

A computerized data base of LLW leaching data has been developed. Long-term tests on portland cement, bitumen and vinyl ester-styrene (VES) polymer waste forms containing simulated wastes are underway which are designed to identify and evaluate factors that accelerate leaching without changing the mechanisms.

This report presents highlights of major projects in the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Radio-frequency and microwave technology are dealt with. The p-bar gravity experiment, accelerator theory and simulation activities, the Proton Storage Ring, and the Fusion Materials Irradiation Test accelerator are discussed. Activities on the proposed LAMPF II accelerator, the BEAR (Beam Experiment Aboard Rocket) project, beam dynamics, the National Bureau of Standards racetrack microtron, and the University of Illinois racetrack microtron are covered. Papers published by AT-Division personnel during this reporting period are listed.

In 1974, a modest program for funding new, innovative research was initiated at ORNL. It was called the ''Seed Money'' program and has become part of a larger program, called Exploratory R and D, which is being carried out at all DOE national laboratories. This report highlights 12 accomplishments of the Seed Money Program: nickel aluminide, ion implantation, laser annealing, burn meter, Legionnaires' disease, whole-body radiation counter, the ANFLOW system, genetics and molecular biology, high-voltage equipment, microcalorimeter, positron probe, and atom science. (DLC)

There is considerable debate over the ability of electric generation capacity to meet the growing needs of the US economy in the 1990s. This study provides new perspective on that debate and examines the possibility of power outages resulting from electricity supply constraints. Previous studies have focused on electricity supply growth, demand growth, and on the linkages between electricity and economic growth. This study assumes the occurrence of electricity supply shortfalls in the 1990s and examines the steps that homeowners, businesses, manufacturers, and other electricity users might take in response to electricity outages.

Calculations were done applying ENDF data to the German AVR pebble bed reactor at KFA. Several core models were used, and the results obtained with ORNL methods for the multiplication, reaction rates, temperature coefficient of reactivity, and fuel temperature distributions are reported and compared. Only a small difference in multiplication is found for this core in going from ENDF/B-IV to ENDF/B-V cross-section data. The temperature coefficients calculated with the ENDF/B-V are somewhat smaller in magnitude. The worth of control rods was obtained and only a small difference was found with the data, but the calculated results are high compared with experiment. Neutron reaction rates with the key actinides are reported for three-dimensional core calculations.

Optical emission spectra from high-purity Pu-242 were generated with a glovebox-enclosed inductively coupled plasma (ICP) source. Spectra covering the 2280 to 7008 Angstrom wavelength range are presented along with general commentary on ICP-Pu spectroscopy.

Since 1958, CO{sub 2} concentrations at Mauna Loa Observatory have been obtained using a nondispersive, dual detector, infrared gas analyzer. Air samples are obtained from air intakes at the top of four 7m towers and one 27m tower. Those involved in the monitoring project have attempted to improving sampling techniques, reduce possible contamination sources, and adjust data to represent uncontaminated, true conditions throughout the twenty-eight year sampling period. The gas analyzer is calibrated by standardized CO{sub 2}-in-nitrogen reference gases twice daily. Flask samples are taken twice a month for comparison to the data recorded using the infrared gas analyzer. Data are scrutinized daily for possible contamination and archived on magnetic tape for further scrutiny and adjustment. Daily, monthly, and annual averages are computed for the Mauna Loa data after deletion of contaminated samples and readjustment of the data. These averages have shown a steady rise in annual average concentration from 316 parts per million by volume (ppmv) in 1959 to 346 ppmv in 1986.

The following five chapters in this report have been processed separately for inclusion in the Energy Data Base: (1) theoretical model of convective diffusion of motile and non-motile bacteria toward solid surfaces; (2) interfacial electrochemistry of oxide surfaces in oil-bearing sands and sandstones; (3) effects of sodium pyrophosphate additive on the ''huff and puff''/nutrient flooding MEOR process; (4) interaction of Escherichia coli B, B/4, and bacteriophage T4D with Berea sandstone rock in relation to enhanced oil recovery; and (5) transport of bacteria in porous media and its significance in microbial enhanced oil recovery.

Abstract: Contained herein are bibliographies of Sources of experimental and correlated thermodynamic data for seven binary aqueous mixtures of industrial importance, namely mixtures of CO2, H2S, NH3, H2S0, H3P4, CuCl2 and ZnCl2 with water. The categories of equilibrium data included in the bibliographies are activity and osmotic coefficients, equilibria in solution, enthalpies and heat capacity data, vapor-liquid equilibria, and phase equilibrium data.

A bounce-averaged Monte Carlo operator is presented that simulates bounce-averaged perturbative Lorentz pitch angle scattering of particles in toroidal plasmas, in particular a tokamak. In conjunction with bounce-averaged expressions for the deterministic motion, this operator allows a quick and inexpensive simulation on time scales long compared to a bounce time. An analytically tractable model of transport due to toroidal magnetic field ripple is described.

This lecture discusses the events leading to, during, and following the Chernobyl Reactor number 4 accident. A description of the light water cooled, graphite moderated reactor, the reactor site conditions leading to meltdown is presented. The emission of radioactive effluents and the biological radiation effects is also discussed. (FI)

A quantitative calculation is presented that shows where high-kinetic-energy symmetric fission occurs and why it is associated with a sudden and large decrease in fission half-lives. The study is based on calculations of potential-energy surfaces in the macroscopic-microscopic model and a semi-empirical model for the nuclear inertia. For the macroscopic part a Yukawa-plus-exponential model is used and for the microscopic part a folded-Yukawa single-particle potential is used. The three-quadratic-surface parameterization generates shapes for which the potential-energy surfaces are calculated. The use of this parameterization and the use of the finite-range macroscopic model allows for the study of two touching spheres and similar shapes. The results of the calculations in terms of potential-energy surfaces and fission half-lives are presented for heavy even nuclei. The surfaces are displayed in the form of contour diagrams as functions of two moments of the shape. 53 refs., 15 figs., 1 tab.

The decay properties of nuclei in many cases depend strongly on the quantum numbers of the single-particle levels in the vicinity of the Fermi surface. A striking illustration is the prolonged fission half-lives of odd nuclei relative to their even neighbors. The hindrance factor depends on the spin of unpaired odd particle and increases with increasing spin of the odd particle. The effect has been studied theoretically. For /sup 257/Fm the hindrance factor is almost ten orders of magnitude. The computer code for calculating nuclear masses calculates single-particle levels at the deformations considered as one step in the calculations. This code has been run for all nuclei considered in the 1981 mass study and the calculated single-particle levels were stored on permanent mass storage. This is actually point (I.D.1) in the research plan ('UNIFIED MODEL ...'). A computer code has been constructed for extracting levels of nuclei that are specified to the program and plotting them. Four such plots are included in this report as figs. 1-4. The levels are plotted relative to the Fermi surface of each nucleus. It is clear from the pictures that for /sup 257/Fm the calculations predict the N = 157 neutron orbital to have …

The decay properties of nuclei in many cases depend strongly on the quantum numbers of the single-particle levels in the vicinity of the Fermi surface. A striking illustration is the prolonged fission half-lives of odd nuclei relative to their even neighbors. The hindrance factor depends on the spin of unpaired odd particle and increases with increasing spin of the odd particle. The effect has been studied theoretically. For /sup 257/Fm the hindrance factor is almost ten orders of magnitude. The computer code for calculating nuclear masses calculates single-particle levels at the deformations considered as one step in the calculations. We have run this code at the ground state deformation of all nuclei considered in the 1981 mass study and stored the calculated single-particle levels on permanent mass storage. A computer code has been constructed for extracting levels of nuclei that are specified to the program and plotting them. In this report we consider single-proton levels for even-N nuclei in the range 152 less than or equal to N less than or equal to 162. Six such plots are included in this report. The levels are plotted relative to the Fermi surface of each nucleus. We also include tables of the …

This final report is the result of a study initiated in 1976 to obtain washability data for Alaskan coals, to supplement the efforts of the US Department of Energy in their ongoing studies on washability of US coals. Washability characteristics were determined for fifty coal samples from the Northern Alaska, Chicago Creek, Unalakleet, Nenana, Matanuska, Beluga, Yentna and Herendeen Bay coal fields. The raw coal was crushed to 1-1/2 inches, 3/8 inch, 14 mesh and 65 mesh top sizes, and float-sink separations were made at 1.30, 1.40 and 1.60 specific gravities. A limited number of samples were also crushed to 200 and 325 mesh sizes prior to float-sink testing. Samples crushed to 65 mesh top size were also separated at 1.60 specific gravity and the float and sink products were characterized for proximate and ultimate analyses, ash composition and ash fusibility. 72 refs., 79 figs., 57 tabs.

After of the transuranic elements are removed from complex concentrate waste by the TRUEX process, the remaining waste will be grouted for final storage. The purpose of this project, conducted at the Pacific Northwest Laboratory (PNL), is to support a future decision to grout the complexant waste without destroying the organic contents. In work performed this year, it has been demonstrated that grouts with acceptable parameters for the Transportable Grout Facility can be made using actual waste. The acceptability of these grouts from a regulatory view seems to be less of a problem than was thought at this time last year. None of the organics found in the waste are included on the US Environmental Protection Agency's Hazardous Chemicals List. 7 refs., 12 figs., 4 tabs.

This report describes the computer simulation of two underwater nuclear explosions, Operation Wigwam and a modern hypothetical explosion of greater yield. The computer simulations were done in spherical geometry with the LASNEX computer code. Comparison of the LASNEX calculation with Snay's analytical results and the Wigwam measurements shows that agreement in the shock pressure versus range in water is better than 5%. The results of the calculations are also consistent with the cube root scaling law for an underwater blast wave. The time constant of the wave front was determined from the wave profiles taken at several points. The LASNEX time-constant calculation and Snay's theoretical results agree to within 20%. A time-constant-versus-range relation empirically fitted by Snay is valid only within a limited range at low pressures, whereas a time-constant formula based on Sedov's similarity solution holds at very high pressures. This leaves the intermediate pressure range with neither an empirical nor a theoretical formula for the time constant. These one-dimensional simulations demonstrate applicability of the computer code to investigations of this nature, and justify the use of this technique for more complex two-dimensional problems, namely, surface effects on underwater nuclear explosions. 16 refs., 8 figs., 2 tabs.

Cyclical variations in barometric pressure cause an oscillatory up-and-down motion of gases within the chimney produced by an underground nuclear test. Analytical and experimental modeling of this atmospheric pumping mechanism has been undertaken to better understand and to quantify the associated rates of cavity gas migration toward the earth's surface and the probable rate of release to the atmosphere. Three different types of models are being investigated: (1) homogeneous porous medium; (2) fractured medium with impermeable matrix blocks; and (3) double-porosity media consisting of fracture networks among porous matrix blocks. A primary purpose is to understand how the oscillatory character of the atmospheric pumping process might significantly enhance the contaminant transport in any or all of the three classes of media. This preliminary report describes some of the analytical, numerical, and experimental work which have been completed.

This report describes the history of monitoring work and the legal framework which applies to employee privacy rights and associate4d issues of worker protection.

Neutron and photon flux spectra have been measured and calculated for the case of neutrons produced by D-T reactions streaming through a cylindrical iron duct surrounded by concrete. Measurements and calculations have also been obtained when the iron duct is partially filled by a laminated stainless steel and borated polyethylene shadow bar. Schematic diagrams of the experimental apparatus is included.

This decontamination and decommissioning (D&D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D&D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

This decontamination and decommissioning (D D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.