In discussion with a number of people at HAPO, KAPL and ANL a hypothesis has been evolved which appears to fit available information concerning irradiation embrittlement of uranium as well as indicate a possible solution to the problem. The purpose of this memorandum is to expound the hypothesis as an aid to those working with the problem. Since it imbodies the ideas of many people, no claim to unique authorship is implied.

Report of the daily cash position for Sugar Land State Bank.

Herman Lurie's weekly report for the sugar market.

Abstract: Fifty-four spectral lines of curium are listed together with estimated intensities. A brief description of the manner of taking the spectra and of measuring the lines are given.

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."

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.

April report of the U.S. Congressional Oversight Panel describing their activities and findings regarding the federal government's current strategy in mitigating the effects of the 2007-2008 financial crisis through the Troubled Asset Relief Fund (TARP).

This letter report is a supplement to the letter reports submitted previously under ECRs No. 2002-600-012 (Borrow Area C) and No. 2002-600-012a (CWC expansion). This letter report covers all areas that may be subject to surface disturbance under Alternative Groups A, B, C, D1, D2, D3, E1, E2, E3, and the No Action Alternative of the Hanford Solid Waste Environmental Impact Statement (HSW EIS), except for the following Low-Level Burial Grounds (LLBGs). The LLBGs proposed for use in the HSW EIS that are not subject of this letter report (218-W-3A, 218-W-3AE, 218-W 4B, 218-W-5, the developed portion of 218-W-4C, and the eastern half [except the northeastern corner] of 218-W-6 in the 200 West Area; and 218-E-10 and 218-E-12B in the 200 East Area) are surveyed annually. Annual letter reports concerning these are currently sent to Mr. Brett M. Barnes of Fluor Hanford, Inc. For the areas of surface disturbance described herein we provide a summary of field survey methods, survey results, and considerations and recommendations based on these results.

Lawrence Livermore National Laboratory (LLNL) is evaluating design alternatives to improve the voltage regulation in our Flash X-Ray (FXR) accelerator cell and pulse-power system. The goal is to create a more mono-energetic electron beam that will create an x-ray source with a smaller spot-size. Studying the interaction of the beam and accelerator cell will generate improved designs for high-current accelerators at Livermore and elsewhere. When an electron beam crosses the energized gap of an accelerator cell, the electron energy is increased. However, the beam with the associated electromagnetic wave also looses a small amount of energy because of the increased impedance seen across the gap. The phenomenon is sometimes called beam loading. It can also be described as a beam-induced voltage at the gap which is time varying. This creates beam energy variations that we need to understand and control. A high-fidelity computer simulation of the beam and cell interaction has been completed to quantify the time varying induced voltage at the gap. The cell and pulse-power system was characterized using a Time-domain Reflectometry (TDR) measurement technique with a coaxial air-line to drive the cell gap. The beam-induced cell voltage is computed by convoluting the cell impedance with measured beam …

Although the current baseline Hanford flowsheet for immobilizing low-activity waste (LAW) assumes borosilicate-based glass, opportunities exist to improve or change this baseline to reduce the current schedule and cost requirements of accomplishing the mission of site cleanup. Development of an alternative glass-forming system can lead to this goal of cost and schedule reduction through enhanced waste loading and higher plant throughput. The purpose of this project is to investigate the iron-phosphate glass system as an alternative for immobilizing Hanford LAW. Previous studies on the iron phosphate glass systems and their potential advantages for immobilizing Hanford LAW have been reviewed and technical uncertainties and data required before implementing this technology have been presented. A team of researchers and engineers from the MO-SCI Corporation, the Pacific Northwest National Laboratory, the Savannah River Technology Center, and the University of Missouri at Rolla has performed a series of tests to address some of the open questions about the potential use of iron phosphate glass for immobilizing Hanford LAW. The results of this team effort are summarized along with recommendations regarding the further laboratory study needs. Additional longer-term testing requirements for implementing the iron phosphate glass-based immobilization process at Hanford are also presented.

This document details activities of the Fuels Preparation Department during the month of March 1961. (FI)

The objective of this test was to irradiate self-supported fuel elements under conditions of severity comparable to those expected for future loadings of this geometry. From this irradiation an attempt was made to determine the resistance to corrosion of cooled cladding, the effect of supports on cladding corrosion and coolant flow patterns, resistance of ``hot-spot`` type of attack, and rupture resistance of projection fuel elements. These results are compared to rib supported control elements in a relative manner. To accomplish this comparison, four shortened columns of 1.47% enriched self-supported fuel were charged into B Reactor on 11-27-59, along with four columns of 1.47% enriched, current geometry fuel under authority of reference 1. As authorized, operating conditions were balanced as closely as possible within equipment and calculational limitations to minimize any ``built-in`` differences between the two materials being compared in order that exposure could be used as the basis for the rupture and corrosion comparisons.

Estimated water flow rates at H Pile for various postulated conditions are given. The conditions under which the data are valid are as follows: (1) the estimated accuracy of the tube flow rates is {+-}5%, and of pile flow rates {+-}7%; (2) the pile flow rates are based upon the present tube geometry, orifice zone pattern and total flow at H Pile; (3) the flow rates should be increased about 2% if film-free slugs and tubes are considered; and (4) flow rates for enlarged fittings are based upon fittings similar in shape to the present H Pile fittings. The maximum tube flow rates for the DR Pile would be about 2% greater than those given in the table for present tube fittings. For enlarged fittings, the rates for DR Pile tube would be the same as those given for H Pile tubes. The ultimate permissible flow will depend, in part, upon limitations on maximum cross-header pressure and maximum tube inlet pressure, and upon the instrumentation necessary to detect abnormal tube flow conditions.

This test is designed to accomplish two primary objectives: (1) to attempt to verify ex-reactor corrosion data which indicated improved corrosion resistance of cast blank X-8001 alloy material compared with wrought blank, and (2) to attempt to verify the resistance to groove pitting type of corrosion attack previously observed on M-388 components. Ex-reactor tests of cast blank M-388 alloy in autoclaves using water as the corrosive media up to 360 C, and in flow loops up to 120 C have indicated that the corrosion resistance of the cast blank material is equivalent to, and probably superior to the corrosion resistance of wrought blank material. Metallographic examination of this material indicated a more uniform nickel dispersion in the aluminum as a probable explanation of this performance. The sporadic occurrence of severe groove pitting has seriously challenged the use of X-8001 nickel aluminum alloy as a fuel element cladding material. Although the actual cause of the groove pitting has not been determined, non-uniform dispersion of the nickel in the alloy is suspected. The cause of the non-uniform nickel dispersion or segregation has been located and virtually eliminated by removal of additional aluminum (scalping) from the ingots prior to fabrication of the components.

Reductions in irradiation costs and increases in production rate have provided a continuing incentive for more efficient operation of the Hanford Piles. These improvements have been obtained by means of higher specific powers, greater water flow rates, and better water utilization. However, the extent of the improvements which can be made in this manner may be limited by such factors as tube and slug corrosion, slug stability, and graphite damage rates at higher operating temperatures. Water purification and pumping costs are also factors to be considered. New slug designs are being developed which may be capable of much higher specific power operation. Higher graphite temperatures may also prove feasible, but the water plant performance limitations for the present single pass cooling systems may prove much more expensive to relieve. The use of recirculating cooling water as a means of attaining higher temperature, higher power operation has received preliminary study. A preliminary economic evaluation of an operating area equipped for recirculation versus single pass cooling is needed to better determine the relative merits of the two cooling methods. This report presents the results of such an evaluation and discusses the direction of future development work in the field of pile cooling.

Volume II of the documentation contains the actual source code of the LDSM submodule, and the cross reference table of its variables. The code is divided into two parts. The first part contains the main part of the source code. The second part lists the INCLUDE files referenced inside the main part of the code.

The ultimate objective of this research has been to uncover novel reagents and experimental conditions for heteroatom removal and hydrogen transfer processes, which would be applicable to the liquefaction of coal under low-severity conditions. To this end, one phase of this research has investigated the cleavage of carbon-heteroatom bonds involving sulfur, oxygen, nitrogen and halogen by subvalent transition-metal complexes. A second phase of the study has assessed the capability of the same transition-metal complexes or of organoaluminum Lewis acids to catalyze the cleavage of carbon-hydrogen bonds in aromatics and hence to promote hydrogen shuttling. Finally, a third phase of our work has uncovered a remarkable synergistic effect of combinations of transition metals with organoaluminum Lewis acids on hydrogen shuttling between aromatics and hydroaromatics. (VC)

This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineering; Appendix D - Non-degree Certificate Program; Appendix E - Curriculum for Associate Degree Program; Appendix F - Curriculum for NCC Program; Appendix G - Information 1991 Teleconference Series; Appendix H - Information on 1992 Teleconference Series; Appendix I - WERC interactive Television Courses; Appendix J - WERC Research Seminar Series; Appendix K - Sites for Hazardous/Radioactive Waste Management Series; Appendix L- Summary of Technology Development of the Second Year; Appendix M - List of Major Publications Resulting from WERC; Appendix N - Types of Equipment at WERC Laboratories.

G. A. Last reports on metallic uranium irradiation studies: cluster irradiations, tubular element irradiations, MTR-ETR irradiations on NaK capsules, effects of pH on film formation, fuel performance, effect of pressure on swelling, and ETR rupture tests. R. D. Leggett reports on irradiation program, and pore site and distribution in irradiated uranium.

In February, 1990, the Secretary of Energy, James Watkins approved a grant for a waste (management) education and research consortium program by New Mexico State University (NMSU) to the US Department of Energy (DOE). This program known by the acronym, ``WERC`` includes NMSU, the University of New Mexico (UNM), the New Mexico Institute of Mining and Technology (NMIMT), Navajo Community College, the Los Alamos National Laboratory and the Sandia National Laboratories. The program is designed to provide an integrated approach to the national need via the following: (1) Education in waste management to reach thousands of students by the three Consortium universities and the affiliate college resulting in graduate, undergraduate, and associate degrees with concentration in environmental management. (The term waste or environmental management is used in a broad sense throughout this paper and includes all aspects of environmental management and environmental restoration.) (2) Professional development via teleconference for industry and government. (3) Technology development programs at the leading edge, providing training to students and information to faculty feeding into the education programs. (4) Education and technology development at the campuses, as well as from four field sites. (5) Ties with other multidisciplinary university facilities. (6) Ties with two National …

The objective of this test is to irradiate an NPR fuel element inner tube in the ETR 3 {times} 3 Loop. the NPR fuel element is a tube in tube type. Both tubes are Zircaloy-2 clad uranium metal. The inner tube is identified by the Hanford designation NINI. In GEH-10-43 we plan to measure an NINI tube after each cycle for four cycles. An NPR inner tube with slightly larger diameter has been run in the ETR Hanford 3 {times} 3 Loop. Two NINI elements are now running in the 3 {times} 3 Loop.

The main objectives of this proposed research work are to refine further the inverse liquid chromatography technique for the study of surface properties of raw coals, treated coals and coal minerals in water, to evaluate relatively surface properties of raw coals, treated coals and coal minerals by inverse liquid chromatography, and to evaluate flotability of various treated coals in conjunction with surface properties of coals. Coals such as Pittsburgh seam coal, Illinois No. 6 coal, Wyodak coal are chosen as representatives of high-rank bituminous coal, high volatile bituminous coal and subbituminous coal, respectively. Coal minerals such as pyrite and dolomite are chosen as representative coal minerals.

The purpose of this report is to define the objectives of the model, describe its basic approach, and provide detail on how it works. The EFP is a regulatory accounting model that projects electricity prices. The model first solves for revenue requirements by building up a rate base, calculating a return on rate base, and adding the allowed expenses. Average revenues (prices) are calculated based on assumptions regarding regulator lag and customer cost allocation methods. The model then solves for the internal cash flow and analyzes the need for external financing to meet necessary capital expenditures. Finally, the EFP builds up the financial statements. The EFP is used in conjunction with the National Energy Modeling System (NEMS). Inputs to the EFP include the forecast generating capacity expansion plans, operating costs, regulator environment, and financial data. The outputs include forecasts of income statements, balance sheets, revenue requirements, and electricity prices.

The National Energy Modeling System (NEMS) is a computer modeling system developed by the Energy Information Administration (EIA). The NEMS produces integrated forecasts for energy markets in the United States by achieving a general equilibrium solution for energy supply and demand. Currently, for each year during the period from 1990 through 2010, the NEMS describes energy supply, conversion, consumption, and pricing. The Electricity Market Module (EMM) is the electricity supply component of the National Energy Modeling System (NEMS). The supply of electricity is a conversion activity since electricity is produced from other energy sources (e.g., fossil, nuclear, and renewable). The EMM represents the generation, transmission, and pricing of electricity. The EMM consists of four main submodules: Electricity Capacity Planning (ECP), Electricity Fuel Dispatching (EFD), Electricity Finance and Pricing (EFP), and Load and Demand-Side Management (LDSM). The ECP evaluates changes in the mix of generating capacity that are necessary to meet future demands for electricity and comply with environmental regulations. The EFD represents dispatching (i.e., operating) decisions and determines how to allocate available capacity to meet the current demand for electricity. Using investment expenditures from the ECP and operating costs from the EFD, the EFP calculates the price of electricity, accounting …