Analyses of sludge and soluble waste samples and the inventory of sludge and soluble waste have been used to estimate the concentration of technetium-99 (Tc-99) in sludge solids and soluble waste. These data were also used to establish if the source term assumptions for Tc-99 in the Defense waste Processing Facility (DWPF) flowsheet are accurate and determine the fraction of the Tc-99 inventory in the waste that is soluble. This analysis was needed to establish if the present basis for decontaminated salt feed to the saltstone process is correct. These results and the projected leach rate for Tc-99 from saltstone can then be used to establish if Tc-99 must be removed from contaminated supernate.

Federal regulations and Rockwell Hanford Operations (Rockwell) planning documents require that radioactive waste sites disposed in-place be permanently marked. A number of technical studies have addressed the materials to be used for permanent markers as well as the design configurations. Criteria and standards for markers have also been prepared and issued in draft form. The next step in marker development requires laboratory and field testing of prototype markers. This document provides design specifications for the first generation surface and subsurface markers. At the conclusion of testing activities, definitive specifications can be prepared. Included herein are specifications for marker placement, marker materials, marker configuration and dimensions and marker messages. This document presents specifications only and does not provide rationale or justification for the specifications. Such rationale and justification is available in referenced documents.

This note presents the results of EGS calculations for the temperature rise in an iron beam position monitor strip in the SLC arcs for a 50 GeV incident electron beam. Temperature rises of about 830/sup 0/C per pulse are possible for 50..mu.. (Gaussian sigma) beams of 5 x 10/sup 10/ electrons per pulse if the angle of incidence is great (i.e., around 30 mradians).

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The objective of this work is to explore the technoeconomic feasibility of a series of unit operations involving: (1) wet grinding of coal in water; (2) removal of chlorine and sodium, release of undesirable mineral matter, and chemical incorporation, if needed, of a disposable liquefaction catalyst in coal via hot water teatment; (3) oil agglomeration to dewater and deash coal while retaining most of the pyrite; and (4) solvent drying of coal agglomerates to eliminate oxidation of coal, improve coal liquefaction reactivity, save energy and prepare the coal/solvent slurry for liquefaction. An apparatus capable of running five microautoclaves simultaneously has been designed and constructed. The autoclaves are shaken along the long axis to insure good mixing and pressure and temperature can be monitored in each autocalve during the run. Reproducibility experiments indicate that the standard deviation on the conversion to THF solubles is about 2.5 percent. The standard deviations in conversions to preasphaltenes and asphaltenes are much higher. A five-autoclave experiment has confirmed earlier results which indicate that wet grinding and hot-water treatment have little effect on conversion to THF solubles but that oil agglomeration followed by drying in a vacuum oven causes a large increase and oil agglomeration followed …

The purpose is to estimate the central-cell parameters that can be reached by injection of low-energy neutral beams. The main advantages of low energy (2-keV full-energy component) over high energy (15-keV full-energy component) are the following: (1) creation of a beam-fueled, potentially confined, central-cell plasma (n approx. = 10/sup 13/ cm/sup -3/, E/sub ic/ approx. = 1 keV, T/sub ec/ approx. = 0.4 keV) without the use of cold-gas injection or ICRH heating; and (2) reduced shielding requirement against neutrals external to the plasma. The reasons for these expectations are the larger ionization cross section and plasma radius (normalized to ion gyroradius) for low-energy compared to high-energy beams.

This paper reviews several areas in which corrosion problems have occurred and what can be done to help improve future performance: BWR pipe cracking, PWR steam generators, Three Mile Island-thiosulfate contamination, secondary side problems, mechanical damage (Ginna), piping and vessel cracking, turbine cracking, and bolting. The safety and operational issues involved are listed. (DLC)

This is a design document for the Timing and Control Monitor System Upgrade Project. This project is intended to provide a replacement system for the existing user Encoder Monitor Systems and Varian 72 Control Room computer systems. All of these systems reside at the Nevada Test Site. The function of the T and C Monitor System is to gather real-time statistics and data on user defined key variables from control, communication, data acquistion systems, and from the monitoring system itself. The control, communication, and data acquisition systems each operate separately from the monitor system. The T and C Monitor System gathers this data in order to verify the readiness of an event to begin countdown. This includes setup, verification, calibration, and peripheral services, report any failures that may occur during the countdown, verify detonation and containment, and assist reentry activities after the event.

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