The goal of this project is to find countermeasures to protect High Efficiency Particulate Air (HEPA) filters, in exit ventilation ducts, from the heat and smoke generated by fire. Initially, methods were developed to cool fire-heated air by fine water spray upstream of the filters. It was recognized that smoke aerosol exposure to HEPA filters could also cause disruption of the containment system. Through testing and analysis, several methods to partially mitigate the smoke exposure to the HEPA filters were identified. A continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. The technique is capable of protecting HEPA filters over the total time duration of the test fires. The reason for success involved the modification of the prefiltration media. Commercially available filter media has particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, rolling filter media were laminated with the desired properties. The approach was Edisonian, but truncation in short order to a combination of prefilters was effective. The application of this technique was qualified, since it is of use only to protect HEPA filters from fire-generated smoke aerosols. It is not believed that this technique is cost effective in …

A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)

A new class of numerical algorithms for computer simulation of low frequency electromagnetic and electrostatic phenomena in magnetized plasma is presented. Maxwell's equations are solved in the limits of quasineutrality and negligible transverse displacement current (Darwin's model). Electrons are modeled as a fluid with polarization effects ignored. Ions are described as particles. A novel feature of these algorithms is the use of the electron fluid equation of motion to determine the electric field, which renders these numerical schemes remarkably simple and direct. The simulation plasma is either periodic or bounded by particle reflecting conducting walls. Both fully nonlinear codes with spatial grids and linearized gridless codes have been implemented.

Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)

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The 6'' long final focus beam position monitors (short FF BPM's are longer, thus deliver more signal after a 15 nanosecond filter, than either the Linac or Arc monitors. The purpose of this note is to compare the resolution of the Arc vs Linac electronics when applied to a short FF 2'' diameter BPM. A method of calibrating the Arc modules is also tested and briefly discussed. The range of each DAC setting to minimize digitization error is also calculated.

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The 100-F-33, 146-F Aquatice Biology Fish Ponds waste site was an area with six small rectangular ponds and one large circular pond used to conduct tests on fish using various mixtures of river and reactor effluent water. The current site conditions achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification and applicable confirmatory sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

Proton nuclear magnetic resonance (NMR) is used in the Earth Sciences as a means of obtaining information about the molecular-scale environment of fluids in porous geological materials. Laboratory experiments were conducted to advance our fundamental understanding of the link between the NMR response and the geochemical properties of geological materials. In the first part of this research project, we studied the impact of both the surface-area-to-volume ratio (S/V) of the pore space and the surface relaxivity on the NMR response of fluids in sand-clay mixtures. This study highlighted the way in which these two parameters control our ability to use NMR measurements to detect and quantify fluid saturation in multiphase saturated systems. The second part of the project was designed to explore the way in which the mineralogic form of iron, as opposed to simply the concentration of iron, affects the surface relaxation rate and, more generally, the NMR response of porous materials. We found that the magnitude of the surface relaxation rate was different for the various iron-oxide minerals because of changes in both the surface-area-to-volume ratio of the pore space, and the surface relaxivity. Of particular significance from this study was the finding of an anomalously large surface …

The performance of the new combustor was tested. Experiments showed that this combustor has superior insulating quality than the previous one. Measured radial concentrations indicated uniform distribution of the primary fuel (coal) inside the fire tube resulting in reasonably flat concentration profiles. However, measured radial concentrations after the addition of the reburn fuel showed uneven distribution of the fuel resulting in parabolic concentration profiles, an indication of insufficient mixing in the reburn zone. In order to study mechanisms of nitrogenous species destruction in the reburn zone, it is necessary to achieve adequate mixing if the assumption of one dimensional plug flow behavior is to be valid. Thus, it became necessary to modify the injector design and the injection mode of the reburn fuel to achieve an adequate level of mixing which is the focus of this report. The results show that a minimum reburn fuel jet velocity of 15 m/s (standard conditions) was required which is about 80 times the velocity of the primary effluent. The use of nitrogen gas as a transport medium for the reburn fuel was necessary to achieve the desired jet velocities.

This study covers the use of dc generators for meeting the Experimental Power Reactor Ohmic Heating Energy Storage Requirements. The dc generators satisfy these requirements which are the same as defined in WFPS-TME-038 which covered the use of ac generators and homopolar generators. The costs of the latter two systems have been revised to eliminate first-of-a-kind factors. The cost figures for dc generators indicate a need to develop larger machines in order to take advantage of the economy-of-scale that the large ac machines have. Each of the systems has its own favorable salient features on which to base a system selection.

Purpose of this document is to compare and contrast the overall burial costs of the glass and ceramic waste forms, including processing, storage, transportation, packaging, and emplacement in a repository. Amount of waste will require approximately 10,300 standard (24 in. i.d. x 9-5/6 ft length) canisters of waste glass, each containing about 3260 lb of waste at 28% waste loading. The ceramic waste form requires about one-third the above number of standard canisters. Approximately $2.5 billion is required to process and dispose of this waste, and the total cost is independent of waste form (glass or ceramic). The major cost items (about 80% of the total cost) for all cases are capital and operating expenses. The capital and 20-year operating costs for the processing facility are the same order of magnitude, and their sum ranges from about one-half of the total for the reference glass case to two-thirds of the total for the ceramic cases.

The Mark 22 assemblies previously charged to the P Reactor as the P-11 charge, but never irradiated, are stored in borated racks in Building 105-K Assembly Area. The assemblies are stored inside aluminum cans into which they are placed and subsequently dried upon removal from the P-Reactor. This report discusses non-destructive examinations supplemented by destructive examination of a small number of these assemblies made to establish the acceptability of these assemblies for use as the K-15 charge.

Much has been written about ceramic superconductors since their discovery in 1986. Most of this writing reports and describes scientific research. However, some authors have sought to put this research in context: to assess where the field stands, what might be technically feasible, what might be economically feasible, and what potential impacts ceramic superconductors will bring to the electric power sector. This report's purpose is to make the results of already published assessments readily available. To that end, this report lists and provides abstracts for various technical and economic assessments related to applications of High-Temperature Superconductors (HTS) to the electric power sector. Those studies deemed most important are identified and summarized. These assessments were identified by two means. First, members of the Executive Committee identified some reports as worthy of consideration and forwarded them to Argonne National Laboratory. Twelve assessments were selected. Each of these is listed and summarized in the following section. Second, a bibliographic search was performed on five databases: INSPEC, NTIS, COMPENDEX, Energy Science Technology, and Electric Power Database. The search consisted of first selecting all papers related to High Temperature Superconductors. Then papers related to SMES, cables, generators, motors, fault current limiters, or electric utilities were …

The subject of this review is intense ion beam propagation and the possibilities of measuring time dependent ion energy in the beam. Propagation effects discussed include charge separation, charge and current autoneutralization, electron thermalization and current neutralization decay. The interaction of a plasma beam with material obstacles, like collimators, and with transverse magnetic fields is also described. Depending on beam energy, density and pulse length, these interactions can include material ablation with plasmadynamic flow and undeflected propagation across transverse magnetic fields by a polarization drift. On the basis of this review I conclude that three diagnostics: a single floating potential probe, net current probes (Faraday cups) and a Rutherford scattering spectrometer appear capable of giving prompt, time dependent ion energy measurements.

Fragments of radioactive materials were deposited in the Redox area during August, 1953. By radiation monitoring, the location, physical properties, and dosage were determined. The cause was assumed to be the buildup of ammonium nitrate containing ruthenium on the filters of the Redox stack. The amount of occupational exposure, and the reasons why this incident happened were also discussed.

Fluor Daniel Hanford, Inc. (FDH) is currently adopting streamlined business processes through integrated software solutions. Replacing the legacy software (current/replacement systems, attached) also avoids significant maintenance required to resolve Year 2000 issues. This initiative is being referred to as `HANDI 2000`. The software being implemented in the first phase of this project includes Indus International`s PASSPORT Software, Peoplesoft and Primavera P3 Software. The project, which encompasses all the system replacements that will occur, has been named `HANDI 2000.` The PASSPORT applications being implemented are Inventory Management, Purchasing, Contract Management, Accounts Payable, and MSDS (Material Safety Data Sheets).

The intent of this study is to establish more completely the justifications for constructing a decontamination plant as outlined in Budget Item B 5720, ``Containmented Equipment Renovation Shop,`` FY 1957, Plant and Equipment Projects. In particular, the economic incentives have been explored. The question or idea has been investigated of assigning a dollar value to engineering information which might be obtained from examining contaminated equipment which has failed from unknown causes. Heretofore it has not been possible to examine such equipment because suitable decontamination facilities have not been available. An effort has been made to uncover all possible uses for the proposed facility in order that the estimated capital and operating costs might be evaluated in terms of all the functions which the proposed plant might perform.

Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to use tubular dummies for this portion of the support charge which are less expensive to fabricate and which are easily identified during the charging-discharging process. However, there exists a remote possibility that one or more tubular pieces could be inadvertently placed in a rear nozzle resulting in a flow restriction in the process tube. These arrangements of tubular support pieces in the dummy pattern, i.e., tubulars positioned against the fuel column and/or in the process tube rear nozzles, have been hydraulically tested to determine if there is adequate and unrestricted flow at normal operating header pressures.

The objective of this irradiation is to further verify the corrosion rate of tubular-type fuel elements under conditions of high specific power and central core temperatures. This fuel will be the inner tube only of an NPR fuel assembly. As in previous tests, this inner tube rupture will be used to further substantiate the rupture detection instrumentation that is being used in the development of the NPR. Previously unirradiated fuel will be used in this test. The reactor is to operate at full power during the test. Permission is requested for charging two tubular elements The top element will have attached to it a hydraulic mechanism for opening a defect in the outer surface of the tube. The second or bottom element, will be used as a heater element to maintain loop temperature.

This engineering study looks at the solids/liquids separation unit operations after the acid dissolution of the K Basin sludge treatment. Unit operations considered were centrifugation, filtration (cartridge, cross flow, and high shear filtration) and gravity settling. The recommended unit operations for the solids/liquids separations are based upon the efficiency, complexity, and off-the-shelf availability and adaptability. The unit operations recommended were a Robatel DPC 900 centrifuge followed by a nuclearized 31WM cartridge filter. The Robatel DPC 900 has been successfully employed in the nuclear industry on a world wide scale. The 31WM cartridge filter has been employed for filtration campaigns in both the government and civilian nuclear arenas.

This engineering study evaluates the use of physical separation technologies to separate organic ion exchange resin from KE Basin sludge prior to nitric acid dissolution. This separation is necessitate to prevent nitration of the organics in the acid dissolver. The technologies under consideration are: screening, sedimentation, elutriation. The recommended approach is to first screen the Sludge and resin 300 microns then subject the 300 microns plus material to elutriation.

The surveillance photography of underground nuclear detonations at NTS was engineered by EG&G to furnish the following information on unexpected venting: (1) establish when, with respect to zero time, the venting occurred; (2) record the point or points of emission of the venting gases; (3) show the colors, if any, of the venting gases; (4) the direction of cloud travel; and (5) dimensions and volume of the cloud as a function of time. In addition, the film records provide a color documentary film including a record of gross surface motion and a record of unexpected surface phenomenon (such as in Longshot). Surveillance coverage starts at minus 5 seconds and continues to plus 30 minutes. This report describes the typical photographic program setup, films used, and film processing.

The objective of this test is to measure the emergency reactor flow through the high pressure crosstie line (HPCT) after the removal of the flow limiting orifices in the HPCT. The flow limiting orifices in the HPCT were removed on July 5, 1960, as per Design Change No. 383. The removal of the flow limiting orifice allowed increased emergency flow and brought the crosstie coolant flow more nearly into conformance with the coolant supply reliability criteria. The purpose of this test is to measure emergency flow under certain conditions so that available flow under all conditions may be more precisely determined.