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Radiative Heat Transfer in Pulverized-Coal-Fired Boilers: Development of the Absorptive/Reflective Character of Initial Ash Deposits (open access)

Radiative Heat Transfer in Pulverized-Coal-Fired Boilers: Development of the Absorptive/Reflective Character of Initial Ash Deposits

Emission Fourier transform infrared (FTIR) spectroscopy data provide in situ, time-resolved, spectral emissivity measurements for ash deposits generated from two US Powder River Basin coals under realistic combustion conditions. The first three hours of deposit growth on a tube in cross flow in Sandia`s Multifuel Combustor detail the development of surface emissivity with time. Measured emissivities vary significantly with wavelength, reflecting the influence of the physical, chemical, and optical properties of the deposit. At long wavelengths (>7{mu}m), emission bands exhibit characteristics of sulfates and silicates. The spectral emissivity measured in this region approaches a steady value, indicating that the deposit becomes opaque. In contrast, deposits are not opaque at shorter wavelengths where the measured emissivity is influenced by the properties of the underlying metal surface. Theoretical predictions of the emissivity of a particulate layer were performed and results are compared to the measured values. The theory adequately predicts the general features of spectral variation of the emissivity. The predicted trends in emissivity with particle size and deposit composition are also consistent with experimental observations. Total (Planck-weighted) emissivities are calculated from the measured spectral values for the deposits at flame temperatures. They increase with time from the clean tube value (0.2 …
Date: February 1, 1994
Creator: Richards, G. H.; Harb, J. N.; Baxter, L. L.; Bhattacharya, S.; Gupta, R. P. & Wall, T. F.
Object Type: Article
System: The UNT Digital Library
Radiochemical procedures for analysis of Pu, Am, Cs and Sr in water, soil, sediments and biota samples (open access)

Radiochemical procedures for analysis of Pu, Am, Cs and Sr in water, soil, sediments and biota samples

The Environmental Radioactivity Analysis Laboratory (ERAL) was established as an analytical facility. The primary function of ERAL is to provide fast and accurate radiological data of environmental samples. Over the years, many radiochemical procedures have been developed by the staffs of ERAL. As result, we have found that our procedures exist in many different formats and in many different notebooks, documents and files. Therefore, in order to provide for more complete and orderly documentation of the radiochemical procedures that are being used by ERAL, we have decided to standardize the format and compile them into a series of reports. This first report covers procedures we have developed and are using for the radiochemical analysis of Pu, Am, Cs, and Sr in various matrices. Additional analytical procedures and/or revisions for other elements will be reported as they become available through continuation of these compilation efforts.
Date: February 1, 1994
Creator: Wong, K. M.; Jokela, T. A. & Noshkin, V. E.
Object Type: Report
System: The UNT Digital Library
Radiological performance assessment for the E-Area Vaults at the Savannah River Site, Part 1: Simulation of radionuclide migration in the near-field (open access)

Radiological performance assessment for the E-Area Vaults at the Savannah River Site, Part 1: Simulation of radionuclide migration in the near-field

Two papers presented in this session cover a numerical simulation of radionuclide migration from Savannah River Site`s E-Area Vaults (EAV) to the groundwater. These vaults are constructed below the ground surface and above the historical high water table. This paper covers the simulation of radionuclide migration in the unsaturated zone. A saturated zone model containing aquifers affected by the facility was also developed. The rate (Curies/yr) of radionuclide release to the water table obtained from Part I was used as the source term for the saturated zone model. The migration of 23 key radionuclides for up to two million years was predicted [Westinghouse 1994]. The calculated annual dose of each of the radionuclides due to ingestion of water, based on unit initial inventory, is reported in Part II.
Date: February 1, 1994
Creator: Yu, A. D.; Cook, J. R.; Lam, P. S.; Wilhite, E. L. & Smith, C. S.
Object Type: Article
System: The UNT Digital Library
The Radiological Safety Analysis Computer Program (RSAC-5) user`s manual. Revision 1 (open access)

The Radiological Safety Analysis Computer Program (RSAC-5) user`s manual. Revision 1

The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user`s manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods.
Date: February 1, 1994
Creator: Wenzel, D. R.
Object Type: Report
System: The UNT Digital Library
Rapid prototyping applications at Sandia National Laboratories (open access)

Rapid prototyping applications at Sandia National Laboratories

In an effort to reduce the cycle time for producing prototypical mechanical and electro-mechanical components, Sandia National Laboratories has integrated rapid prototyping processes into the design and manufacturing process. The processes currently in operation within the Rapid Prototyping Laboratory are Stereolithography (SL), Selective Laser Sintering (SLS), and Direct Shell Production Casting (DSPC). These emerging technologies have proven to be valuable tools for reducing lead times and fabrication costs. Sandia uses the SL and SLS processes to support internal product development efforts. Their primary use is to fabricate patterns for investment casting in support of a Sandia-managed program called FASTCAST that integrates computational technologies and experimental data into the investment casting process. These processes are also used in the design iteration process to produce proof-of-concept models, hands-on models for design reviews, fit-check models, visual aids for manufacturing, and functional parts in assemblies. The DSPC process is currently being developed as a method of fabricating ceramic investment casting molds directly from a CAD solid model. Sandia is an Alpha machine test site for this process. This presentation will provide an overview of the SL and SLS processes and an update of our experience and success in integrating these technologies into the product …
Date: February 1, 1994
Creator: Atwood, C. L.; McCarty, G. D.; Pardo, B. T. & Bryce, E. A.
Object Type: Article
System: The UNT Digital Library
Reactor pressure vessel structural integrity research in the US Nuclear Regulatory Commission HSST and HSSI Programs (open access)

Reactor pressure vessel structural integrity research in the US Nuclear Regulatory Commission HSST and HSSI Programs

This report discusses development on the technology used to assess the safety of irradiation-embrittled nuclear reactor pressure vessels containing flaws. Fracture mechanics tests on reactor pressure vessel steel have shown that local brittle zones do not significantly degrade the material fracture toughness, constraint relaxation at the crack tip of shallow surface flaws results in increased fracture toughness, and biaxial loading reduces but does not eliminate the shallow-flaw fracture toughness elevation. Experimental irradiation investigations have shown that the irradiation-induced shift in Charpy V-notch versus temperature behavior may not be adequate to conservatively assess fracture toughness shifts due to embrittlement and the wide global variations of initial chemistry and fracture properties of a nominally uniform material within a pressure vessel may confound accurate integrity assessments that require baseline properties.
Date: February 1, 1994
Creator: Pennell, W.E. & Corwin, W.R.
Object Type: Article
System: The UNT Digital Library
Reactor-pumped laser facility at DOE`s Nevada Test Site (open access)

Reactor-pumped laser facility at DOE`s Nevada Test Site

The Nevada Test Site (NTS) is one excellent possibility for a laser power beaming site. It is in the low latitudes of the US, is in an exceptionally cloud-free area of the southwest, is already an area of restricted access (which enhances safety considerations), and possesses a highly-skilled technical team with extensive engineering and research capabilities from underground testing of our nation`s nuclear deterrence. The average availability of cloud-free clear line of site to a given point in space is about 84%. With a beaming angle of {plus_minus}60{degree} from the zenith, about 52 geostationary-orbit (GEO) satellites could be accessed continuously from NTS. In addition, the site would provide an average view factor of about 10% for orbital transfer from low earth orbit to GEO. One of the major candidates for a long-duration, high-power laser is a reactor-pumped laser being developed by DOE. The extensive nuclear expertise at NTS makes this site a prime candidate for utilizing the capabilities of a reactor pumped laser for power beaming. The site then could be used for many dual-use roles such as industrial material processing research, defense testing, and removing space debris.
Date: February 1, 1994
Creator: Lipinski, R. J.
Object Type: Article
System: The UNT Digital Library
Realizing parallel reduction operations in Sisal 1.2 (open access)

Realizing parallel reduction operations in Sisal 1.2

A parallel job consists of sets of concurrent and sequential tasks. Often the tasks compute sets of values that are reduced to a single value or gathered to build an aggregate structure. Since reductions may introduced dependencies, most languages separate computation and reduction. For example, Fortran 90 and HPF provide a rich set of predefined reduction functions, but only for extant arrays. Sisal 1.2 is unique in that reduction is a natural consequence of loop expressions. Unfortunately, the language supports only seven reduction operations. In this paper, the authors present compilation techniques that recognize pairs of for expressions in Sisal 1.2 as computation-reduction expressions. The techniques work without any language or intermediate form extensions; however, they recognize only certain forms. They describe how they implement pairs of computation-reduction expressions as single parallel loops, and they present performance numbers that demonstrate the utility of their techniques.
Date: February 1, 1994
Creator: Denton, S. M.; Feo, J. T. & Miller, P. J.
Object Type: Article
System: The UNT Digital Library
Recent DIII-D high power heating and current drive experiments (open access)

Recent DIII-D high power heating and current drive experiments

This paper describes recent DIII-D high power heating and current drive experiments. Describes are experiments with improved wall conditioning, divertor particle pumping, radiative divertor experiments, studies of plasma shape and high poloidal beta.
Date: February 1, 1994
Creator: Simonen, T. C.; Jackson, G. L.; Mahdavi, M. A.; Petrie, T. W.; Politzer, P. A.; Taylor, T. S. et al.
Object Type: Article
System: The UNT Digital Library
Reformulated gasoline: Costs and refinery impacts (open access)

Reformulated gasoline: Costs and refinery impacts

Studies of reformulated gasoline (RFG) costs and refinery impacts have been performed with the Oak Ridge National Laboratory Refinery Yield Model (ORNL-RYM), a linear program which has been updated to blend gasolines to satisfy emissions constraints defined by preliminary complex emissions models. Policy makers may use the reformulation cost knee (the point at which costs start to rise sharply for incremental emissions control) to set emissions reduction targets, giving due consideration to the differences between model representations and actual refining operations. ORNL-RYM estimates that the reformulation cost knee for the US East Coast (PADD I) is about 15.2 cents per gallon with a 30 percent reduction of volatile organic compounds (VOCs). The estimated cost knee for the US Gulf Coast (PADD III) is about 5.5 cents per gallon with a VOC reduction of 35 percent. Reid vapor pressure (RVP) reduction is the dominant VOC reduction mechanism. Even with anti-dumping constraints, conventional gasoline appears to be an important sink which permits RFG to be blended with lower aromatics and sulfur contents in PADD III. In addition to the potentially large sensitivity of RFG production to different emissions models, RFG production is sensitive to the non-exhaust VOC share assumption for a particular …
Date: February 1, 1994
Creator: Hadder, G. R.
Object Type: Report
System: The UNT Digital Library
Regional Atmospheric Transport Code for Hanford Emission Tracking (RATCHET). Hanford Environmental Dose Reconstruction Project (open access)

Regional Atmospheric Transport Code for Hanford Emission Tracking (RATCHET). Hanford Environmental Dose Reconstruction Project

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses that individuals may have received from operations at the Hanford Site since 1944. This report deals specifically with the atmospheric transport model, Regional Atmospheric Transport Code for Hanford Emission Tracking (RATCHET). RATCHET is a major rework of the MESOILT2 model used in the first phase of the HEDR Project; only the bookkeeping framework escaped major changes. Changes to the code include (1) significant changes in the representation of atmospheric processes and (2) incorporation of Monte Carlo methods for representing uncertainty in input data, model parameters, and coefficients. To a large extent, the revisions to the model are based on recommendations of a peer working group that met in March 1991. Technical bases for other portions of the atmospheric transport model are addressed in two other documents. This report has three major sections: a description of the model, a user`s guide, and a programmer`s guide. These sections discuss RATCHET from three different perspectives. The first provides a technical description of the code with emphasis on details such as the representation of the model domain, the data required by the model, and the equations used to make …
Date: February 1, 1994
Creator: Ramsdell, J. V. Jr.; Simonen, C. A. & Burk, K. W.
Object Type: Report
System: The UNT Digital Library
Regulating toxicity in drilling mud: An innovative approach using pollution prevention (open access)

Regulating toxicity in drilling mud: An innovative approach using pollution prevention

Both in terms of volume and toxic pollutants, drilling muds and drill cuttings are the most significant waste streams from exploratory and development activities in the oil and gas industry. Under the Clean Water Act, the US Environmental Protection Agency (EPA) regulates discharges of all contaminants, including drilling muds, into the waterways and offshore areas of the United States. EPA employs technology-based effluent standards in issuing discharge permits to both onshore and offshore operators. This paper examines the regulatory approaches used by EPA to limit toxicity in drilling muds at offshore drilling platforms and discusses other measures EPA has adopted to reduce toxicity of drilling muds discharged offshore. This effort focuses on an innovative approach that emphasizes pollution prevention used by EPA Region X for offshore Alaska, which is contrasted with a more traditional command and control regulatory approach used by other EPA regional offices. The Region X approach includes collection of influent and effluent data, development of a comprehensive data base of technical information, and prescription of specific mud formulas. This influent-effluent approach reduces uncertainty and guesswork, enhances use of innovative technology, and lowers toxic discharges compared to the standard EPA command and control approach. The influent-effluent approach provides …
Date: February 1, 1994
Creator: Burke, C. J.
Object Type: Article
System: The UNT Digital Library
RELAP5/MOD3 assessment for calculation of safety and relief valve discharge piping hydrodynamic loads. International agreement report (open access)

RELAP5/MOD3 assessment for calculation of safety and relief valve discharge piping hydrodynamic loads. International agreement report

This report presents an assessment study for the use of the code RELAP 5/MOD3/5M5 in the calculation of transient hydrodynamic loads on safety and relief discharge pipes. Its predecessor, RELAP 5/MOD1, was found adequate for this kind of calculations by EPRI. The hydrodynamic loads are very important for the discharge piping design because of the fast opening of the valves and the presence of liquid in the upstream loop seals. The code results are compared to experimental load measurements performed at the Combustion Engineering Laboratory in Windsor (US). Those measurements were part of the PWR Valve Test Program undertaken by EPRI after the TMI-2 accident. This particular kind of transients challenges the applicability of the following code models: two-phase choked discharge; interphase drag in conditions with large density gradients; heat transfer to metallic structures in fast changing conditions; two-phase flow at abrupt expansions. The code applicability to this kind of transients is investigated. Some sensitivity analyses to different code and model options are performed. Finally, the suitability of the code and some modeling guidelines are discussed.
Date: February 1, 1994
Creator: Stubbe, E. J.; VanHoenacker, L. & Otero, R.
Object Type: Report
System: The UNT Digital Library
Relay test program. Series 2 tests: Integral testing of relays and circuit breakers (open access)

Relay test program. Series 2 tests: Integral testing of relays and circuit breakers

This report presents the results of a relay test program conducted by Brookhaven National Laboratory (BNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC). The program is a continuation of an earlier test program the results of which were published in NUREG/CR-4867. The current program was carried out in two phases: electrical testing and vibration testing. The objective was primarily to focus on the electrical discontinuity or continuity of relays and circuit breaker tripping mechanisms subjected to electrical pulses and vibration loads. The electrical testing was conducted by KEMA-Powertest Company and the vibration testing was performed at Wyle Laboratories, Huntsville, Alabama. This report discusses the test procedures, presents the test data, includes an analysis of the data and provides recommendations regarding reliable relay testing.
Date: February 1, 1994
Creator: Bandyopadhyay, K. K.; Kunkel, C. & Shteyngart, S.
Object Type: Report
System: The UNT Digital Library
Release of radon contaminants from Yucca Mountain: The role of buoyancy driven flow (open access)

Release of radon contaminants from Yucca Mountain: The role of buoyancy driven flow

The potential for the repository heat source to promote buoyancy driven flow and thereby cause release of radon gas out of Yucca Mountain has been examined through a critical review of the theoretical and experimental studies of this process. The review indicates that steady-state buoyancy enhanced release of natural radon and other contaminant gases should not be a major concern at Yucca Mountain. Barometric pumping and wind pumping are identified as two processes that will have a potentially greater effect on surface releases of gases.
Date: February 1, 1994
Creator: Sullivan, T.M. & Pescatore, C.
Object Type: Report
System: The UNT Digital Library
The remedial investigation of marine sediment at the United Heckathorn Superfund site (open access)

The remedial investigation of marine sediment at the United Heckathorn Superfund site

The former United Heckathom site in Richmond, California, was used to process and package chlorinated pesticides from the 1940s to the mid-1960s. These activities resulted in the contamination of upland soils and marine sediment in the adjacent waterways. Battelle/Marine Sciences Laboratory (MSL) was requested by USEPA to conduct a remedial investigation and feasibility study (RI/FS). of the marine portion of the site. The objectives of this RI are to determine the extent of pesticide contamination in inner Richmond Harbor, estimate the total volume of contaminated sediment, characterize the subsurface geology; characterize the biological effects of contaminated sediment; and characterize the quality of effluent derived from dewatered sediment through treatability testing. Sediment cores were collected from 53 stations. Vertical subsamples from each sediment core were analyzed for chlorinated pesticides. Sediment from selected cores was also analyzed for other contaminants. Younger Bay Mud (YBM) sediment from multiple stations was mixed to form composite samples representing various segments of the study area. These composites were used for solid-phase toxicity and bioaccumulation tests, and the preparation of liquid-phase samples for treatability testing. The probable quality of effluent produced by dewatering sediment was evaluated by chemical and toxicological testing of suspended-particulate-phase (SPP) and elutriate samples.
Date: February 1, 1994
Creator: White, P. J.; Kohn, N. P.; Gardiner, W. W. & Word, J. Q.
Object Type: Report
System: The UNT Digital Library
Remedial Investigation Report on the Abandoned Nitric Acid Pipeline at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Energy Systems Environmental Restoration Program; Y-12 Environmental Restoration Program (open access)

Remedial Investigation Report on the Abandoned Nitric Acid Pipeline at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Energy Systems Environmental Restoration Program; Y-12 Environmental Restoration Program

Upper East Fork Poplar Creek Operable Unit 2 consists of the Abandoned Nitric Acid pipeline (ANAP). This pipeline was installed in 1951 to transport liquid wastes {approximately}4800 ft from Buildings 9212, 9215, and 9206 to the S-3 Ponds. Materials known to have been discharged through the pipeline include nitric acid, depleted and enriched uranium, various metal nitrates, salts, and lead skimmings. During the mid-1980s, sections of the pipeline were removed during various construction projects. A total of 19 locations were chosen to be investigated along the pipeline for the first phase of this Remedial Investigation. Sampling consisted of drilling down to obtain a soil sample at a depth immediately below the pipeline. Additional samples were obtained deeper in the subsurface depending upon the depth of the pipeline, the depth of the water table, and the point of auger refusal. The 19 samples collected below the pipeline were analyzed by the Oak Ridge Y-12 Plant`s laboratory for metals, nitrate/nitrite, and isotopic uranium. Samples collected from three boreholes were also analyzed for volatile organic compounds because these samples produced a response with organic vapor monitoring equipment. Uranium activities in the soil samples ranged from 0.53 to 13.0 pCi/g for {sup 238}U, from …
Date: February 1, 1994
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Remnant voltages in the RHIC storage system during acceleration: Part 2 (open access)

Remnant voltages in the RHIC storage system during acceleration: Part 2

None
Date: February 1, 1994
Creator: Connolly, R. & Rose, J.
Object Type: Report
System: The UNT Digital Library
A remotely operated robot for decontamination tasks (open access)

A remotely operated robot for decontamination tasks

Engineers in the Robotics Development Group at the Westinghouse Savannah River Company (WSRC) have developed a robot which will be used to decontaminate a pipe gallery of a tank farm used for nuclear waste storage. Personnel access is required into this pipe gallery to inspect existing pipes and perform repairs to secondary containment walls around the tank farm. Presently, the pipe gallery is littered with debris of various sizes and its surface is contaminated with activity levels up to 2.5E6 DPM (disintegrations per minute) alpha and exposure levels as high as 20 Rad/hr. Cleaning up this pipe gallery win be the mission of an all-hydraulic robotic vehicle developed in-house at WSRC caged the ``Remote Decon`` robot. The Remote Decon is a tracked vehicle which utilizes skid steering and features a six-degree-of-freedom (DOF) manipulator arm, a five-DOF front end loader type bucket with a rotating brush for scrubbing and decontaminating surfaces, and a three-DOF pan/tilt mechanism with cameras and lights. The Remote Decon system is connected to a control console via a 200 foot tethered cable. The control console was designed with ergonomics and simplicity as the main design factors and features three joysticks, video monitors, LED panels, and audible alarms.
Date: February 1, 1994
Creator: Dudar, A. M. & Vandewalle, R. C.
Object Type: Article
System: The UNT Digital Library
Research on the stability, electronic properties, and structure of a-Si:H and its alloys. Annual subcontract report, 1 June 1992--31 May 1993 (open access)

Research on the stability, electronic properties, and structure of a-Si:H and its alloys. Annual subcontract report, 1 June 1992--31 May 1993

This report describes work focusing on the defect and transport properties of a-Si:H with particular emphasis on defect metastability. Light-induced defects remain the major impediment to higher stabilized solar cell efficiencies. The many years of research have shown that this is a difficult problem to solve, and we take the view that a solution can be found only with a deep understanding of the mechanism; this has been our main goal. The metastability is closely related to the intrinsic defect properties, so these studies have also led to a greatly improved model of all the electronic properties of a-Si:H. Section A of the report discusses a theoretical analysis of the defect pool model for the equilibrium dark defect density, with particular reference to whether there are significant charged defects. Section B discusses the use of an electronic transport model to analyze forward and reverse currents and extends it to the calculation of field dependences of bulk and contact currents, which give more precision to the analysis of defects from reverse bias thermal generation currents. Electronic transport is discussed in Section C. Work done on H transport and bonding is described in Section D.
Date: February 1, 1994
Creator: Jackson, W. B.; Johnson, N. & Nickel, N.
Object Type: Report
System: The UNT Digital Library
Research priorities for occupational radiation protection (open access)

Research priorities for occupational radiation protection

The Subpanel on Occupational Radiation Protection Research concludes that the most urgently needed research is that leading to the resolution of the potential effects of low-level ionizing radiation. This is the primary driving force in setting appropriate radiation protection standards and in directing the emphasis of radiation protection efforts. Much has already been done in collecting data that represents a compendium of knowledge that should be fully reviewed and understood. It is imperative that health physics researchers more effectively use that data and apply the findings to enhance understanding of the potential health effects of low-level ionizing radiation and improve the risk estimates upon which current occupational radiation protection procedures and requirements depend. Research must be focused to best serve needs in the immediate years ahead. Only then will we get the most out of what is accomplished. Beyond the above fundamental need, a number of applied research areas also have been identified as national priority issues. If effective governmental focus is achieved on several of the most important national priority issues, important occupational radiation protection research will be enhanced, more effectively coordinated, and more quickly applied to the work environment. Response in the near term will be enhanced and …
Date: February 1, 1994
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Resolution of iterative inverses in seismic tomography (open access)

Resolution of iterative inverses in seismic tomography

With applications to seismic traveltime tomography in mind, methods have been developed for computing both the model and data resolution matrices for iterative inverse such as those produced by the Lanczos scheme for finding a matrix inverse.
Date: February 1, 1994
Creator: Berryman, J. G.
Object Type: Article
System: The UNT Digital Library
Resolving the Ferrocyanide Safety Issue at the Hanford Site (open access)

Resolving the Ferrocyanide Safety Issue at the Hanford Site

Considerable data have been obtained on the chemical and physical properties of ferrocyanide waste stored in Hanford Site single-shell tanks (SSTs). Theoretical analyses and ferrocyanide waste simulant studies have led to the development of fuel, moisture, and temperature criteria that define continued safe storage. Developing the criteria provides the technical basis for closing the Ferrocyanide Unreviewed Safety Question (USQ). Using the safety criteria, the ferrocyanide tanks have been ranked into one of three safety categories: Safe, Conditionally Safe, and Unsafe. All the ferrocyanide tanks are currently ranked in either the Safe or Conditionally Safe categories. Analyses of core samples taken from three ferrocyanide tanks have shown cyanide concentrations about a factor of ten lower than predicted by the original flowsheets. Hydrolytic and radiolytic destruction (aging) of the ferrocyanide matrix has occurred during the 35 plus years the waste has been stored at the Hanford Site. Because of waste aging, it is possible that all of the ferrocyanide tanks may now contain less than the 8 wt % sodium nickel ferrocyanide specified in the fuel criterion for the Safe category. Ferrocyanide tanks that remain in the Conditionally Safe category may require monitoring and surveillance to verify that the waste remains in …
Date: February 1, 1994
Creator: Meacham, J. E.; Cash, R. J. & Babad, H.
Object Type: Article
System: The UNT Digital Library
Resource characterization and residuals remediation, Task 1.0: Air quality assessment and control, Task 2.0: Advanced power systems, Task 3.0: Advanced fuel forms and coproducts, Task 4.0 (open access)

Resource characterization and residuals remediation, Task 1.0: Air quality assessment and control, Task 2.0: Advanced power systems, Task 3.0: Advanced fuel forms and coproducts, Task 4.0

This report addresses three subtasks related to the Resource Characterization and Residuals Remediation program: (1) sulfur forms in coal and their thermal transformations, (2) data resource evaluation and integration using GIS (Geographic Information Systems), and (3) supplementary research related to the Rocky Mountain 1 (RM1) UCG (Underground Coal Gasification) test program.
Date: February 1, 1994
Creator: Hawthorne, S. B.; Timpe, R. C. & Hartman, J. H.
Object Type: Report
System: The UNT Digital Library