From the point of view of predicting melting behavior of fuel elements containing fission products after 50 percent burn-up, the fuel can be considered to consist of 2000 moles Th, 150 moles U, 55 moles of rate earth metal, 31 moles of Zr, 25 moles of Mo, 20 moles of Rh-Ru-Tc, and 15 moles of alkaline earth metal. All other fission products are present in too small amounts to have any important effect upon the melting point or will have vaporized. However, the presence of alkali metal vapor should be considered.

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1975, activities, membership, finances, organizational leadership, and other information about scouting programs.

Several potential hazards that have been recognized and anticipated in the design and fabrication of the pressure vessel in the Homogeneous Reactor Test are discussed. These hazards results from the high operating pressure and temperature of the reactor, the exposure of the reactor vessel material to potential embrittlement and other affects of fast-neutron irradiation, and the need for containment of corrosive flowing liquids. The steps taken in recognition of these hazards are also discussed. The applicability of present codes to the reactor vessel fabrication is considered. Additional fields are suggested where recommended practices developed by code writing bodies could assist in development-type reactor design and fabrication.

In the memorandum entitled "Stored Energy in BNL Reactor Graphite", dated February 25, 1953, there is described an experiment conducted by Gurinsky's group to determine the energy per gram of irradiated graphite released in a 200°C anneal. Similar experiments were subsequently conducted by W. Kosiba, differing from the original in two particulars: a) Instead of two graphite samples, one normal, and one irradiated, Kosiba used only an irradiated sample which he heated first to release the stored energy, and then again after the energy was released. In this way, he obtained time against temperature curves for both normal and irradiated graphite from the same sample. (These curves are graphed for each run in Figs. 1 thru 5.) b) The vycor tubing used in the original experiment was not used by Kosiba. Five runs of this experiment were selected, Runs 4P, 13, 36, and 40 at furnace temperatures of 200°C, and Run 45 at a furnace temperature of 400°C.

The distribution of thermal neutrons in a W slug having a one centimeter aluminum end cap has been calculated on the basis of simple diffusion theory. It is found that the average neutron density, and therefore the power output, at the end of the slug is about 34% higher than the density far from the end cap. This result agrees well with the recent Argonne pile experiments (CP-1729).

In making various experimental heat studies a power producing metal slug is simulated by a slug with a graphite rod electrode of 3/8" diameter inserted lengthwise through it. There is a helium filled annular space between the graphite and the inner surface of the slug cylinder. Radiant heat passes from the electrode to the metal; with proper adjustment of the electrode current the slug in the steady state will therefor "produce" the same amount of energy from its exterior surface as it would under operating conditions. The question arises, however, as to how uniform the electrode temperature is along its length. And also, in some cases one end of the electrode is embedded in the slug metal; it is then desirable to know how much heat flows by conduction from the electrode into the slug.

Monthly report documenting Imperial Sugar operational expenses for the year, broken down by actual sales and production, with estimated operational numbers for the remainder of the year.

Sugar Stock and Sales report for Imperial Sugar Company including a list of sugar sales for the date showing the amounts and estimated balance separated by location, raw sugar, and refined sugar sales.

A set of coupled rate equations for densities and energies in a tandem mirror machine have been incorporated into a fast-running code. The code is suitable for parameter-searching and studying time-dependent processes. The code has been used to study buildup of thermalized alphas in a tandem mirror reactor, and cyclic schemes for limiting the alpha population. The principal findings are: Q/sub av/ is drastically reduced as alphas build up from a steady-state in which alphas were artificially eliminated; running in a pulsed mode to clean out alphas improves the time-averaged Q significantly, but not enough; elimination of 80% of the alphas by nonadiabatic loss and running in pulsed mode allows a reasonable time-averaged Q.

Seven different fluorophosphate glass compositions were doped with cerium and terbium. Initial results indicated that these glasses, as they stood, had only a limited ability to dissolve the rare earth ions. A series of melt modifications was attempted to improve the solubility. (MHR)

The physical vulnerability system for evaluating probable damage from a nuclear blast has received wide acceptance because it is a simple but general system applicable to a wide variety of target classes. A series of hand-calculator programs using this system that permit equally accurate but faster calculations than the conventional handbook method are described. The programs cover various interrelationships among peak overpressures, peak dynamic pressures, vulnerability numbers, weapons radii, and kill probability. The use of a programmable calculator greatly reduces the chance of operator error by eliminating individual hand calculations and graphical determinations of parameter values.

Program demonstration and user instructions are presented for FabryVB5. This computer program was created for use in analyzing Fabry-Perot interferometer records that detail the velocity time histories of fast moving surfaces. Graphical curves representing peak fringe positions and fiducial timing dots are extracted from a digitized film record or from a CCD digital image. An analysis is demonstrated on a sample velocimeter record along with some mathematical formula and routine operations. Routines used to analyze calibration records on streak camera distortions are illustrated in an appendix. This is a Microsoft Visual Basic{trademark} version for the PC.

During last twenty years, a number of models have been used to calculate the change of conductivity and dielectric strength in materials caused by the passage of high-energy photons, such as Gamma-rays and X-rays. In these models, the electromagnetic fields generated in the electronic system created by the high-energy photons have not been investigated. That is, the solution of Maxwell's equations has not been obtained for these kinds of problems. We constructed a theoretical model, described by a set of equations to solve such a problem. The model includes the equations that describe the physics of the recombination and generation of electron-hole pairs by the high-energy photons in the dielectric materials, the Compton electron generation rates, and Maxwell's equations. When a beam of gamma photons penetrates into a transmission line or cables, energetic electrons and holes (carriers) are created in the metals and dielectrics of the system by the Compton and photoelectric effects. These energetic electrons and holes in turn create many low-energy holes and electrons through the interaction of the high-energy electrons with the atoms in the solids. Since the density of the solids is very high, the mean free path of the high-energy electrons is very short. In …

The purpose of this paper is to report the methodology and assumptions, data, and results of calculations concerning safety and environmental issues related to excursions to currently planned NIF operations. Many possible uses of NIF have been suggested over the years. While some of these possible uses have been adopted into the baseline plans for NIF, many others have not. While we do not yet know all of the possible approved uses for NIF, one of the items that would bear on whether a certain course use might be adopted or not would be its environmental and safety impact. Here we examine certain excursions from the existing planned operations to determine their environmental and safety impacts. These excursions are related to the use of ''cocktail'' hohlraums as the baseline target for ignition experiments in the National Ignition Facility (NIF) as well as possible increased utilization of beryllium and uranium. This paper also addresses the fission products produced from cocktail hohlraum use for high yield experiments. Again, this analyses does not imply an authorization to proceed with such modes of operation, or any intent to proceed beyond this analyses. A detailed analysis of a range of postulated experiments for NIF was …

AQUATECH Systems, a business unit of Allied-Signal Inc., proposes to demonstrate the technical viability and cost effectiveness of the SOXAL process a combined SO{sub x}/NO{sub x} control process on a 3 MW equivalent flue gas slip stream from Niagara Mohawk Power Corporation, Dunkirk Steam Station Boiler No. 4, a coal fired boiler. The SOXAL process combines 90+% sulfur dioxide removal from the flue gas using a sodium based scrubbing solution and regeneration of the spent scrubbing liquor using AQUATECH Systems` proprietary bipolar membrane technology. This regeneration step recovers a stream of sulfur dioxide suitable for subsequent processing to salable sulfur or sulfuric acid. Additionally 90+% control of NO{sub x} gases can be achieved in combination with conventional urea/methanol injection of NO{sub 2} gas into the duct. The SOXAL process is applicable to both utility and industrial scale boilers using either high or low sulfur coal. The SOXAL demonstration Program began September 10, 1991 and is approximately 22 months in duration.

The objective of this program is the experimental study of interactions of low energy, highly charged ions with other atomic species. The Cornell superconducting solenoid, cryogenic electron beam ion source CEBIS designed and built in our laboratory is the major piece of apparatus used in these investigations. This progress report describes the work accomplished during the period April 16, 1994 and August 1, 1994. This includes both finished experiments and preparatory work for planned future experiments using the source. During this time, we have completed measurements of the angular distributions and energy gains in Ar{sup q+} (11{le}q{le}14) on Ar collisions at 72 qeV laboratory energy. In particular, energy gain spectra at different laboratory scattering angles were obtained for Ar({sup q-1}){sup +} projectiles, i.e. projectiles whose final charge state had decreased by one unit. The experimental technique used, and the method of analysis are described elsewhere. The raw spectra are similar to those observed for Ar{sup 8+} and Ar{sup l0+} on Ar at comparable energies, as well as those described in the last progress report for Ar{sup l2+} on Ar.

This report documents the chemical compatibility of waste types within tanks 241-C-106, 241-AY-101, and 241-AY-102. This information was compiled to facilitate the transfer of tank C-106 waste to tank AY-102 utilizing supernatant from AY-101 as the sluicing medium. This document justifies that no chemical compatibility safety issues currently understood, or theorized from thermodynamic modeling, will result from the intended sluice transfer operation.

Monthly report documenting Imperial Sugar operational expenses for the year, broken down by actual sales and production, with estimated operational numbers for the remainder of the year.

The operation of a Priest Rapids dam is stated to necessitate river flow manipulation varying from 25,000 cfs to 120,000 cfs in the winter months of a critical water year. The low flow may persist for periods of six hours daily, and the expected daily average low flow is 61,000 cfs. The possible effects of this on reactor operation and waste disposal to the Columbia River which are of the interest to the Radiological Sciences Department were reviewed by J.F. Honstead, R.E. Rostenbach, and R.F. Foster. These include radiation hazards in reactor area water treatment plants, reactor area drinking water contamination; increased river temperature; chromium pollution problems; effects on downstream river usage, and effects on aquatic life.

A synergistic supercritical extraction process was developed and its feasibility demonstrated using a semi-batch extraction process unit. The process was found to be effective in selectively cleaning organic sulfur from Ohio coals. Optimal case involved a mixture of CO{sub 2}, H{sub 2}O, and CH{sub 3}OH, and the removal of organic sulfur ranged from 35 to 55%. Combined with pyrite and mineral matter removal by gravity, the resulting coals would have 20--30% increased heating values and SO{sub 2} emissions would be down to 1.2--1.5 pounds per million Btu, thus meeting compliance requirements. Estimated cleaning cost including pyrite removal is $25 to 45 per ton. The most important cost factor is the operation at high pressures.

Department of Energy Participation in the Rawlins UCG Demonstration Project began officially on November 9, 1987. Even though their financial participation began at this time, they will receive technical information from the start of the project which was on January 1, 1987. The Rawlins UCG Demonstration Project is progressing in Phase I with the majority of the emphasis on facility design, site characterization and the environmental work. The site characterization field work is estimated to be completed by the end of February with the final report completion towards the end of Phase I. The facility design effort is close to the 40% level. It is anticipated that all permits will be applied for in Phase I and most of them will be granted by the end of Phase I. The obtaining of the private financing continues to be a major activity in the project. All of the financing must be in place before the continuation for DOE funding to Phase II will be applied for.

The safety assessment for rotary mode core sampling was developed using certain bounding assumptions, however, those assumptions were not verified for each of the existing or potential flammable gas tanks. Therefore, a Flammable Gas/Rotary Mode Core Sampling Approved Checklist has been completed for tank 241-TX-113 prior to sampling operations. This transmittal documents the dispositions of the checklist items from the safety assessment.

The purpose of this test was to evaluate the behavior of natural lithium-bearing materials and to provide samples for production and extraction information. Testing of the target elements was done in conjunction with a test evaluating the behavior of NIEl fuel elements. Conditions for operation during the test were similar to, or more severe, than conditions expected in N Reactor.

The attached tables are an extension of the data that will be used in the forthcoming Production Studies. It considers thorium load substitution for the natural uranium cases previously reported. The power level, operating efficiency, exposure, conversion ratios, tonnage, and production are given for the natural U loading, blanket loading, and full conversion. The small reactors, the C reactor, and the K reactor are considered.