At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constituents of the waste, and from most of the fission products. The cerium and the trivalent rare earths must then be separated from each other. In the case of cerium recovery, it is necessary to remove the trivalent rare earths in order to maximize the specific activity of the cerium. If promethium is the desired product, a preliminary cerium separation is desirable to protect the ion-exchange resin (used for separating promethium from its adjacent rare earths) from the intense high-energy radiation from cerium.

Stresses set up by an insulating strip in the bond are estimated and found to be small compared to those normally present without the defect.

Technical report with six sections describing the process: (1) The reaction of HN)3 with HSCN; (2) The distribution of nitric acid between hexone and water; (3) The distribution of HSCN between hexone and water; (4) The solubility of thorium sulfate in various extraction solutions; (5) The distribution of protoactinium and fission elements between hexone and aqueous thiocyanate solutions; and (6) Separation of uranium from thorium by extraction into hexone as UO2(SCH)a.

Abstract. A neutron diffraction crystal spectrometer with a resolution of 13 microseconds per meter and monochromatic beam intensity up to 10(4)n/cm(2)=sec in the range 0.012-0.400 ev has been constructed for study of the activation cross section of Be7 as a function of energy in the thermal region. First preliminary results using ZnS(Ag) as a detector suggest the possibility of a resonance for the Be7(n,p)Li7 reaction in the region of 0.025-0.050 ev.

Technical report covering the Homogeneous Reactor Experiment (HRE) reactor physics and engineering, out-of-pile corrosion, in-pile studies, recombination of hydrogen and oxygen, HRE chemical studies, experimental programs for the HRE, and long-range studies. [From Summary]

This technical report details and outlines the BGRR facility's operations and performance record over a period of twelve years. The author of this report finds that the reactor is "one of the most stable and dependable in the business." The report includes two figures.

The DT fusion neutron irradiation of two LLL superconductor wires at 4.2/sup 0/K is described. The sample position, beam-on time, and neutron dose record are given. The results from four ''profile'' dosimetry foils measuring the lateral variation in neutron flux are included.

This quarterly report discusses the technical progress of a US Department of Energy (DOE) Innovative Clean Coal Technology (ICCT) Project demonstrating advanced tangentially-fired combustion techniques for the reduction of nitrogen oxide (NO{sub x}) emissions from a coal-fired boiler. The project is being conducted at Gulf Power Company's Plant Lansing Smith Unit 2 located near Panama City, Florida. The primary objective of this demonstration is to determine the long-term effects of commercially available tangentially-fired low NO{sub x} combustion technologies on NO{sub x} emissions and boiler performance. A target of achieving fifty percent NO{sub x} reduction using combustion modifications has been established for the project. The stepwise approach that is being used to evaluate the NO{sub x} control technologies requires three plant outages to successively install the test instrumentation and the different levels of the low NO{sub x} concentric firing system (LNCFS). Following each outage, a series of four groups of tests are performed. These are (1) diagnostic, (2) performance, (3) long-term, and (4) verification. These tests are used to quantify the NO{sub x} reductions of each technology and evaluate the effects of those reductions on other combustion parameters such as particulate characteristics and boiler efficiency.

The DT fusion neutron irradiation of an AI sample capsule containing cobalt, zirconium, gold, iron, nickel and niobium samples plus two LLL pyrographite samples, and eight LLL silica pieces is described. The sample position, beam-on time, and neutron dose record are given. The maximum neutron fluence on any sample was 2.41 x 10/sup 17/ neutrons/cm/sup 2/.

Various factors that can affect thermal blooming in stagnation zones are examined, including stagnation-zone motion, longitudinal air motion in the neighborhood of the stagnation zone, and the effects of scenario noncoplanarity. Of these effects, only the last offers any reasonable hope of reducing the strong thermal blooming that normally accompanies stagnation zones; in particular, noncoplanarity should benefit multipulse more than cw beams. The methods of treating nonhorizontal winds hydrodynamically for cw and multipulse steady-state sources are discussed. Pulse ''self-blooming'' in the triangular pulse approximation is discussed in the context of both single and multipulse propagation. It is shown that self-blooming and multipulse blooming cannot be treated independently.

(1) LLNL measured the material removal rate from stainless steel, silicon carbide, rhenium, N5, hastalloy X, and titanium as a function of pulse fluence at a wavelength of 810 nm for pulse durations of 150 fs, 1.5 ps, 20 ps, and 500 ps. The spot size of the beam used was 150 microns in diameter and the nominal material thickness was 1-2 mm. These experiments were performed on the existing 1 kHz laser system. Holes of different penetration depths were obtained to ascertain change in removal rate as a function of depth. Measurements included electron microscopy of selected samples. (2) The experiments in I were repeated for all materials but select pulse durations with the sample in a vacuum of base pressure 10 mTorr to determine if hole quality and ablation rate is improved. (3) LLNL measured material removal rate from stainless steel, silicon carbide, rhenium, N5, hastalloy X, and titanium as a function of pulse fluence at a wavelength of 532 nm for pulse duration at 200 ns. The spot size of the beam used was 200 microns in diameter and the material thickness was the same as in task I. Holes of different penetration depths were obtained to …

The DT fusion neutron irradiation of eight LLL Nb-lZr tensile specimens, two BPNL wire-foil packets, eleven BNL-LASL superconductor wires, four LASL high purity single crystals (one each of YAG, Spinel, Al/sub 2/O/sub 3/ and MgO), seven LLL Suprasil and several LLL micro cover glasses. The sample position, beam--on time, and neutron dose record are given. The maximum neutron fluence on any sample was 4.68 x 10/sup 17/ neutrons/cm/sup 2/.

The DT fusion neutron irradiation of nine LLL stainless steel samples (including six tensile specimens), four LASL high purity single crystals (one each of MgO, YAG, Sapphire and Spinel), ten LLL silica samples, and seven LLL calcium fluoride samples is described. The sample position, beam-on time, and neutron dose record are given. The maximum neutron fluence on any sample was 1.39 x 10/sup 17/ neutron/cm/sup 2/.

This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory Work.

Borehole Data Package for Wells 299-W22-48, 299-W22-49, and 299-W22-50 at Single-Shell Tank Waste Management Area S-SX

This report addresses a study that was performed to develop a more economical method of machining damage-free beryllium components at Rocky Flats

This report presents the data resulting from a series of mirror damage tests conducted with the FLEX laser at KMS Fusion on March 14 through March 20, 1990 for Los Alamos National Laboratory. The FLEX laser consists of a ND:YLF master oscillator and four Nd:glass rod amplifiers operating at 1.05 {mu}m. For this program, the laser was configured to produce a 3 ms long square wave envelope of mode locked pulses which was focused onto Los Alamos supplied targets via a 1200 mm focal length (f/20) lens at approximately normal incidence. The pulse energy and spot size were specified by Los Alamos personnel, the energy varying from approximately 10--40 Joules and the spot size ranging from approximately 100--300 {mu}m. A total of 63 target shots and 19 calibration and/or test shots were conducted.

The purpose of this memorandum is to document the improvements and modifications made to the Replacement Costs of Crude Oil (REPCO) Supply Analysis System. While some of this work was performed under our previous support contract to DOE/ASFE, we are presenting all modifications and improvements are presented here for completeness. The memo primarily documents revisions made to the Lower-48 Onshore Model. Revisions and modifications made to other components and models in the REPCO system which are documented elsewhere are only highlighted in this memo. Generally, the modifications made to the Lower-48 Onshore Model reflect changes that have occurred in domestic drilling, oil field costs, and reserves since 1982, the date of the most recent available data used for the original Replacement Costs report, published in 1985.

The attenuation of solar radiation by the atmosphere between the heliostat and receiver of a Central Receiver solar energy system has been computed for a number of atmospheric conditions and tower-heliostat distance.

The description of the three-nucleon system in terms of nucleon and {Delta} degrees of freedom is extended to allow for explicit pion production (absorption) from single dynamic {Delta} de-excitation (excitation) processes. This mechanism yields an energy dependent effective three-body hamiltonean. The Faddeev equations for the trinucleon bound state are solved with a force model that has already been tested in the two-nucleon system above pion-production threshold. The binding energy and other bound state properties are calculated. The contribution to the effective three-nucleon force arising from the pionic degrees of freedom is evaluated. The validity of previous coupled-channel calculations with explicit but stable A isobar components in the wavefunction is studied.

This fieldwork assignment was created to assess the library and information services at the National Laboratories and to understand their organizational structures and the role of the library within those structures. The author`s goal was to collect the data and to evaluate the data and make appropriate recommendations for improving the quality of service at Lawrence Livermore National Laboratory Library. The objectives were: To develop a questionnaire which will be used in the reference interview; to contact a knowledgeable staff person at each facility and collect the information services data from that person; to identify innovative and unique services; to identify non-traditional methods of delivering information services to the scientific clientele; to obtain any user feedback on the services provided; and to identify the organization structure of each of the National laboratories and to determine the role of the library within those structures.

A brazed end closure is currently being used on prototypical NPR fuel elements. The production closure will use a braze alloy composed of 5% Be + 95% Zry-2 to braze the Zircaloy-2 cap to the jacket and to the metallic uranium core. A similar MTR test, a GEH-4-57, 58, used a braze alloy of the composition 4% Be + 12% Fe + 84% Zry-2 which melts at a lower temperature. In this previous test, element GEH-4-57 failed through a cladding defect located at the base of the braze heat affected zone. Because of this failure it would be desirable to subject a fuel element, which had been subjected to more severe brazing conditions, to the same conditions as GEH-4-57, 58. For this reason the thermal conditions of this test essentially match those of GEH-4-57, 58. This irradiation test consists of two identical fuel elements. The fuel material is normal metallic uranium, Zircaloy-2 clad of the tubular geometry, NPR inner size. The fuel was coextruded at Hanford by General Electric`s Fuels Preparation Department. Each element is 10.8 inches in length with flat Zircaloy-2 end caps brazed to the jacket and uranium core with the 5 Be + 95 Zry-2 brazing alloy, …

AMAX Research & Development Center (AMAX R&D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.

This quarterly report discusses the technical progress of a US Department of Energy (DOE) Innovative Clean Coal Technology (ICCT) Project demonstrating advanced tangentially-fired combustion techniques for the reduction of nitrogen oxide (NO{sub x}) emissions from a coal-fired boiler. The project is being conducted at Gulf Power Company`s Plant Lansing Smith Unit 2 located near Panama City, Florida. The primary objective of this demonstration is to determine the long-term effects of commercially available tangentially-fired low NO{sub x} combustion technologies on NO{sub x} emissions and boiler performance. A target of achieving fifty percent NO{sub x} reduction using combustion modifications has been established for the project. The stepwise approach that is being used to evaluate the NO{sub x} control technologies requires three plant outages to successively install the test instrumentation and the different levels of the low NO{sub x} concentric firing system (LNCFS). Following each outage, a series of four groups of tests are performed. These are (1) diagnostic, (2) performance, (3) long-term, and (4) verification. These tests are used to quantify the NO{sub x} reductions of each technology and evaluate the effects of those reductions on other combustion parameters such as particulate characteristics and boiler efficiency.