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Sulfur removal in advanced two stage pressurized fluidized bed combustion. Technical report, 1 March--31 May 1994 (open access)

Sulfur removal in advanced two stage pressurized fluidized bed combustion. Technical report, 1 March--31 May 1994

The objective of this study is to obtain data on the rates of reaction between hydrogen sulfide (H{sub 2}S) and uncalcined calcium-based sorbents under operating conditions relevant to first stage (carbonizer) of Advanced Two-Stage Pressurized Fluidized-Bed Combustors (PFBC). In these systems the CO{sub 2} partial pressure in the first stage generally exceeds the equilibrium value for calcium carbonate decomposition. Therefore, removal of sulfur compounds takes place through the reaction between H{sub 2}S and calcium carbonate. To achieve this objective, the rates of reaction between hydrogen sulfide and uncalcined calcium-based sorbents will be determined by conducting tests in pressurized thermogravimetric analyzer (TGA) and high-pressure/high-temperature fluidized-bed reactor (HPTR) units. The effects of sorbent type, sorbent particle size, reactor temperature and pressure, and CO{sub 2} and H{sub 2}S partial pressures on the sulfidation reaction rate will be determined. During this quarter a series of sulfidation tests were conducted in the high-pressure/high-temperature fluidized-bed reactor (HPTR) units. The effects of sorbent type, sorbent particle size, reactor temperature and pressure, and CO{sub 2} and H{sub 2}S partial pressures on the sulfidation reaction rate will be determined. During this quarter a series of sulfidation tests were conducted in the high-pressure high-temperature thermogravimetric analyzer (HPTGA unit) using limestone …
Date: September 1, 1994
Creator: Abbasian, J.; Chowdiah, P.; Hill, A. H. & Rue, D. M.
Object Type: Report
System: The UNT Digital Library
Development of novel copper-based sorbents for hot-gas cleanup. [Quarterly] technical report, September 1--November 30, 1993 (open access)

Development of novel copper-based sorbents for hot-gas cleanup. [Quarterly] technical report, September 1--November 30, 1993

The objective of this investigation is to evaluate two novel copper-based sorbents, namely copper-chromium and copper-cerium, for their effectiveness in removing hydrogen sulfide from fuel gas in the temperature range of 650{degree} to 850{degree}C. Such high temperatures will be required for the new generation of gas turbines (inlet >750{degree}C) in Integrated Gasification Combined Cycle (IGCC) systems. The effect of pre-reduction on the performance of the sorbents as well as the rate of different reactions occurring in cyclic sulfidation/regeneration, were studied in a thermogravimetric analyzer (TGA). Sulfidation was conducted with and without H{sub 2} and H{sub 2}O, and with and without pre-reduction in H{sub 2} or H{sub 2}/H{sub 2}O. The results of these tests indicate that reduction and regeneration of both sorbents occurs rapidly. Sulfidation of CuCr{sub 2}O{sub 4}, in H{sub 2}O-free and H{sub 2}-/H{sub 2}O-free gas indicates the possible sulfidation of both copper and chromium. Small quantities of SO{sub 2}, were released during sulfidation suggesting the possible oxidation of H{sub 2}S by the sorbent. Regeneration of the CuCr{sub 2}O{sub 4} was complete while regeneration of the CuO-CeO{sub 2} indicated possible limited sulfate formation.
Date: March 1, 1994
Creator: Abbasian, J.; Hill, A. H.; Flytzani-Stephanopoulos, M. & Li Li
Object Type: Report
System: The UNT Digital Library
Development of novel copper-based sorbents for hot-gas cleanup. Technical report, 1 March--31 May 1994 (open access)

Development of novel copper-based sorbents for hot-gas cleanup. Technical report, 1 March--31 May 1994

The objective of this investigation is to evaluate two novel copper-based sorbents, namely copper-chromium and copper-cerium, for their effectiveness in removing hydrogen sulfide from fuel gas in the temperature range of 650 to 850 C. Such high temperatures will be required for the new generation of gas turbines (inlet > 750 C) in Integrated Gasification Combined Cycle (IGCC) systems. Results of fixed-bed reactor tests conducted in this quarter, indicate that, at 750 C, pre-reduction with H{sub 2} in the presence of H{sub 2}O does not effect the performance of either sorbent for H{sub 2}S removal. For the pre-reduced CuCr{sub 2}O{sub 4} sorbent, copper utilization before the first H{sub 2}S breakthrough is substantially higher in synthesis feed gas mixture than in feed gas containing 30 Vol% H{sub 2}, and slightly lower than in 10 vol% H{sub 2}. In sulfidation-regeneration testing of copper- and additive-rich sorbents, chromium-rich CuO-3Cr{sub 2}O{sub 4} sorbent demonstrated very high H{sub 2}S removal efficiency and high copper conversion levels (comparable to that of the 1:1 molar composition sorbent). Similar results were obtained with the cerium-rich CuO-3CeO{sub 2} sorbent, but only for the first cycle. The H{sub 2}S removal performance of both copper-rich sorbents was inferior to that of …
Date: September 1, 1994
Creator: Abbasian, J.; Hill, A. H.; Flytzani-Stephanopoulos, M. & Li, Z.
Object Type: Report
System: The UNT Digital Library
Development of novel copper-based sorbents for hot-gas cleanup. [Quarterly] technical report, December 1, 1993--February 28, 1994 (open access)

Development of novel copper-based sorbents for hot-gas cleanup. [Quarterly] technical report, December 1, 1993--February 28, 1994

The objective of this investigation is to evaluate two novel copper-based sorbents, namely copper-chromium and copper-cerium, for their effectiveness in removing hydrogen sulfide from fuel gas in the temperature range of 650{degree} to 850{degree}. Such high temperatures will be required for the new generation of gas turbines (inlet >750{degree}C) in Integrated Gasification Combined Cycle (IGCC) systems. The effect of pre-reduction with H{sub 2}, in the presence of H{sub 2}O on the performance of the sorbents in cyclic sulfidation/regeneration, was studied in a thermogravimetric analyzer (TGA) and in a fixed-bed reactor at 750{degree}C. The results of the TGA tests indicate that pre-reduction of the sorbents is very fast in either 10% or 30% H{sub 2}. Without sorbent pre-reduction, sulfidation consists of two-stages, a reduction-dominating and a sulfidation-dominating stage. Sulfidation apparently takes place before reduction is complete. During regeneration some copper/cerium sulfates may have formed and Cu{sub 2}O may have formed in addition to CuO. The fixed-bed reactor tests show that at 750{degree}C: (1) prereducing the CuO-Cr{sub 2}O{sub 3} with H{sub 2} does not effect the reactivity of the sorbent towards H{sub 2}S at either the high or low H{sub 2} feed gas concentrations and (2) when 30% H{sub 2} was used …
Date: June 1, 1994
Creator: Abbasian, J.; Hill, A. H.; Flytzani-Stephanopoulos, M. & Li, Zhijiang
Object Type: Report
System: The UNT Digital Library
Sulfur removal in advanced two-stage fluidized-bed combustion. [Quarterly] technical report, December 1, 1993--February 28, 1994 (open access)

Sulfur removal in advanced two-stage fluidized-bed combustion. [Quarterly] technical report, December 1, 1993--February 28, 1994

The objective of this study is to obtain data on the rates of reaction between, hydrogen sulfide (H{sub 2}S) and uncalcined calcium-based sorbents under operating conditions relevant to first stage (carbonizer) of Advanced Two-Stage Pressurized Fluidized-Bed Combustors (PFBC). In these systems the CO{sub 2} partial pressure in the first stage generally exceeds the equilibrium value for calcium carbonate decomposition. Therefore, removal of sulfur compounds takes place through the reaction between H{sub 2}S and calcium carbonate. To achieve this objective the rates of reaction between hydrogen sulfide and uncalcined calcium-based sorbents will be determined by conducting tests in pressurized thermogravimetric analyzer (TGA) and high-pressure/high-temperature fluidized-bed reactor (HPTR) units. The effects of sorbent type, sorbent particle size, reactor temperature and pressure, and CO{sub 2} and H{sub 2}S partial pressures on the sulfidation reaction rate will be determined. During this quarter, the high-pressure thermogravimetric analyzer (HPTGA) unit was installed and the shakedown process was completed. Several tests were conducted in the HPTGA unit to establish the operating procedure and the repeatability of the experimental results. Sulfidation by conducting the baseline sulfidation tests. The results are currently being analyzed.
Date: June 1, 1994
Creator: Abbasian, J.; Hill, A. H.; Wangerow, J. R. & Rue, D. M.
Object Type: Report
System: The UNT Digital Library
Sulfur removal in advanced two-staged pressurized fluidized-bed combustion; [Quarterly] report, September 1--November 1993 (open access)

Sulfur removal in advanced two-staged pressurized fluidized-bed combustion; [Quarterly] report, September 1--November 1993

The objective of this study is to obtain data on the rates of reaction between hydrogen sulfide (H{sub 2}S) and uncalcined calcium-based sorbents under operating conditions relevant to first stage (carbonizer) of Advanced Two-Stage Pressurized Fluidized-Bed Combustors (PFBC). In these systems the CO{sub 2} partial pressure in the first stage generally exceeds the equilibrium value for calcium carbonate decomposition. Therefore, removal of sulfur compounds takes place through the reaction between H{sub 2}S and calcium carbonate. To achieve this objective, the rates of reaction between hydrogen sulfide and uncalcined calcium-based sorbents will be determined by conducting tests in pressurized thermogravimetric analyzer (TGA) and high-pressure/high-temperature fluidized-bed reactor (HPTR) units. The effects of sorbent type, sorbent particle size, reactor temperature and pressure, and CO{sub 2} and H{sub 2}S partial pressures on the sulfidation reaction rate will be determined. A pressurized TGA unit has been purchased by IGT for use in this project.
Date: March 1, 1994
Creator: Abbasian, Javad; Hill, Andy H.; Wangerow, James R. & Rue, David M.
Object Type: Report
System: The UNT Digital Library
Spent Fuel Background Report Volume I (open access)

Spent Fuel Background Report Volume I

This report is an overview of current spent nuclear fuel management in the DOE complex. Sources of information include published literature, internal DOE documents, interviews with site personnel, and information provided by individual sites. Much of the specific information on facilities and fuels was provided by the DOE sites in response to the questionnaire for data for spent fuels and facilities data bases. This information is as accurate as is currently available, but is subject to revision pending results of further data calls. Spent fuel is broadly classified into three categories: (a) production fuels, (b) special fuels, and (c) naval fuels. Production fuels, comprising about 80% of the total inventory, are those used at Hanford and Savannah River to produce nuclear materials for defense. Special fuels are those used in a wide variety of research, development, and testing activities. Special fuels include fuel from DOE and commercial reactors used in research activities at DOE sites. Naval fuels are those developed and used for nuclear-powered naval vessels and for related research and development. Given the recent DOE decision to curtail reprocessing, the topic of main concern in the management of spent fuel is its storage. Of the DOE sites that have …
Date: March 1, 1994
Creator: Abbott, D.
Object Type: Report
System: The UNT Digital Library
Spent Fuel Background Report Volume II (open access)

Spent Fuel Background Report Volume II

This Volume II contains tables that describe DOE fuel storage facilities and the fuel contained in those facilities.
Date: March 1, 1994
Creator: Abbott, D.
Object Type: Report
System: The UNT Digital Library
Application of Clean Water (CWA) Section 404 compensatory wetland mitigation under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (open access)

Application of Clean Water (CWA) Section 404 compensatory wetland mitigation under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)

Pursuant to Section 404 of the Clean Water Act (CWA), activities resulting in the discharge of dredge or fill material into waters of the US, including wetlands, require permit authorization from the US Army Corps of Engineers (ACOE). As part of the Section 404 permitting process, compensatory wetland mitigation in the form of wetland enhancement, restoration, or construction may be required to off-set impacts sustained under a Section 404 permit. Under normal circumstances, compensatory mitigation is a relatively straight forward process; however, issues associated with mitigation become more complex at sites undergoing remediation under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), because on-site response/remedial actions involving dredged and fill material are not subject to the formal Section 404 permitting process. These actions are conducted in accordance with the substantive permitting requirements of the ACOE`s Nationwide and individual permitting programs. Wetland mitigatory requirements are determined through application of the US Environmental Protection Agency`s (USEPA`s) 040(b) (1) Guidelines promulgated in 40 CFR Part 230 and are implemented through compliance with substantive permitting requirements during the conduct of response/remedial actions. A programmatic approach for implementing wetland mitigatory requirements is being developed at a former US Department of Energy (DOE) uranium refinery …
Date: June 1, 1994
Creator: Abbott, D. J. & Straub, C. A.
Object Type: Article
System: The UNT Digital Library
Rheological characterization of nuclear waste using falling-ball rheometry (open access)

Rheological characterization of nuclear waste using falling-ball rheometry

Knowledge of the rheological properties of saturated solutions containing solid particles is very important in nuclear waste management technology. For example, the nuclear waste in the Hanford Site high-level radioactive waste tanks contains strong electrolyte solutions with a high concentration of solids. Previous attempt using rotational viscometers to determine the rheology has shown unusual thixotropic and shear thinning behaviors with a lack of reproducibility. Using falling-ball rheometry, the rheology of the undisturbed simulant may be determined with much better reproducibility. In this study, a well-mixed simulant which has similar chemical composition to the actual waste will be tested. Falling-ball size and density will be varied to get data in a wide range of shear rates. To determine the rheogram, several methods will be tried to match the observed data. Based on these tests, a rheogram can be determined from the model and its best-fit parameters. The simulant shows shear-thinning behavior and a yield stress. This would suggest a H-B model. But when fitting to one of the simulants which showed a very low yield stress, the predictions assuming no yield and assuming yield resulted in no improvement in the fit when assuming yield.
Date: July 1, 1994
Creator: Abbott, J. R.; Unal, C.; Stephens, T.; Pasamehmetoglu, K. O.; Graham, A. L. & Edwards, J. N.
Object Type: Article
System: The UNT Digital Library
Flywheel energy storage using superconducting magnetic bearings (open access)

Flywheel energy storage using superconducting magnetic bearings

Storage of electrical energy on a utility scale is currently not practicable for most utilities, preventing the full utilization of existing base-load capacity. A potential solution to this problem is Flywheel Energy Storage (FES), made possible by technological developments in high-temperature superconducting materials. Commonwealth Research Corporation (CRC), the research arm of Commonwealth Edison Company, and Argonne National Laboratory are implementing a demonstration project to advance the state of the art in high temperature superconductor (HTS) bearing performance and the overall demonstration of efficient Flywheel Energy Storage. Currently, electricity must be used simultaneously with its generation as electrical energy storage is not available for most utilities. Existing storage methods either are dependent on special geography, are too expensive, or are too inefficient. Without energy storage, electric utilities, such as Commonwealth Edison Company, are forced to cycle base load power plants to meet load swings in hourly customer demand. Demand can change by as much as 30% over a 12-hour period and result in significant costs to utilities as power plant output is adjusted to meet these changes. HTS FES systems can reduce demand-based power plant cycling by storing unused nighttime capacity until it is needed to meet daytime demand.
Date: April 1, 1994
Creator: Abboud, R. G.; Uherka, K.; Hull, J. & Mulcahy, T.
Object Type: Article
System: The UNT Digital Library
Hazardous materials in Aquatic environments of the Mississippi River basin. Quarterly project status report, 1 January 1994--30 March 1994 (open access)

Hazardous materials in Aquatic environments of the Mississippi River basin. Quarterly project status report, 1 January 1994--30 March 1994

Projects associated with this grant for studying hazardous materials in aquatic environments of the Mississippi River Basin are reviewed and goals, progress and research results are discussed. New, one-year initiation projects are described briefly.
Date: June 1, 1994
Creator: Abdelghani, A.
Object Type: Report
System: The UNT Digital Library
First results from SAGE II (open access)

First results from SAGE II

The Russian-American Gallium solar neutrino Experiment (SAGE) began the second phase of operation (SAGE II) in September of 1992. Monthly measurements of the integral flux of solar neutrinos have been made with 55 tonnes of gallium. The K-peak results of the first five runs of SAGE II give a capture rate of 76{sub {minus}18}{sup +21} (stat) {sub {minus}7}{sup +5} (sys) SNU. combined with the SAGE I result, the capture rate is 74{sub {minus}12}{sup +13} (stat) {sub {minus}7}{sup +5} (sys) SNU. This represents only 56%--60% of the capture rate predicted by different Standard Solar Models.
Date: July 1, 1994
Creator: Abdurashitov, J. N.; Faizov, E. L. & Gavrin, V. N.
Object Type: Report
System: The UNT Digital Library
Cyclotron subharmonics resonant (CSR) heating (open access)

Cyclotron subharmonics resonant (CSR) heating

The cyclotron subharmonics resonant (CSR) heating mechanism is studied using particle simulation codes with an emphasis on the relationship between CSR and the nonlinear Landua damping.
Date: January 1, 1994
Creator: Abe, H.
Object Type: Report
System: The UNT Digital Library
Numerical Studies on Soliton Propagation in the Dielectric Media by the Nonlinear Lorentz Computational Model (open access)

Numerical Studies on Soliton Propagation in the Dielectric Media by the Nonlinear Lorentz Computational Model

Soliton propagation in the dielectric media has been simulated by using the nonlinear Lorentz computational model, which was recently developed to study the propagation of electromagnetic waves in a linear and a nonlinear dielectric. The model is constructed by combining a microscopic model used in the semi-classical approximation for dielectric media and the particle model developed for the plasma simulations. The carrier wave frequency is retained in the simulation so that not only the envelope of the soliton but also its phase can be followed in time. It is shown that the model may be useful for studying pulse propagation in the dielectric media.
Date: June 1, 1994
Creator: Abe, H. & Okuda, H.
Object Type: Report
System: The UNT Digital Library
Numerical studies on the electromagnetic properties of the nonlinear Lorentz Computational model for the dielectric media (open access)

Numerical studies on the electromagnetic properties of the nonlinear Lorentz Computational model for the dielectric media

We study linear and nonlinear properties of a new computer simulation model developed to study the propagation of electromagnetic waves in a dielectric medium in the linear and nonlinear regimes. The model is constructed by combining a microscopic model used in the semi-classical approximation for the dielectric media and the particle model developed for the plasma simulations. It is shown that the model may be useful for studying linear and nonlinear wave propagation in the dielectric media.
Date: June 1, 1994
Creator: Abe, H. & Okuda, H.
Object Type: Report
System: The UNT Digital Library
Scintillating glass fiber neutron senors (open access)

Scintillating glass fiber neutron senors

Cerium-doped lithium-silicate glass fibers have been developed at Pacific Northwest Laboratory (PNL) for use as thermal neutron detectors. By using highly-enriched {sup 6} Li , these fibers efficiently capture thermal neutrons and produce scintillation light that can be detected at the ends of the fibers. Advantages of scintillating fibers over {sup 3}He or BF{sub 3} proportional tubes include flexibility in geometric configuration, ruggedness in high-vibration environments, and less detector weight for the same neutron sensitivity. This paper describes the performance of these scintillating fibers with regard to count rates, pulse height spectra, absolute efficiencies, and neutron/gamma discrimination. Fibers with light transmission lengths (1/e) of greater than 2 m have been produced at PNL. Neutron sensors in fiber form allow development of a variety of neutron detectors packaged in previously unavailable configurations. Brief descriptions of some of the devices already produced are included to illustrate these possibilities.
Date: April 1, 1994
Creator: Abel, K. H.; Arthur, R. J. & Bliss, M.
Object Type: Article
System: The UNT Digital Library
Scintillating glass fiber-optic neutron sensors (open access)

Scintillating glass fiber-optic neutron sensors

Pacific Northwest Laboratory (PNL) has fabricated cerium-activated lithium silicate scintillating fibers via a hot-downdraw process. These fibers, which, as produced, typically have a transmission length (e{sup {minus}1} length) of greater than 2 meters, are found to undergo aging when subjected to room air. The aging, which is complete in a few weeks, reduces the transmission length to the order of 0.5 meter. Because of the high alkali content of the glass (on the order of 20--30 mole % lithia), we have attributed this aging to aqueous corrosion oat the polymer cladding/glass interface. changes in transmission with chemical treatment of the surface support the corrosion model. Fiber transmission performance has been preserved by modifying the hot-downdraw to a double crucible to produce glass-on-glass waveguides.
Date: April 1, 1994
Creator: Abel, K. H.; Arthur, R. J. & Bliss, M.
Object Type: Article
System: The UNT Digital Library
Factors affecting the quality of fish caught by Native Americans in the Zone 6 fishery 1991 through 1993 (open access)

Factors affecting the quality of fish caught by Native Americans in the Zone 6 fishery 1991 through 1993

A program to monitor the salmon and steelhead (Oncorhynchus spp.) fishery in the lower Columbia River (Zone 6 fishery) was initiated in 1991 to respond to questions and comments frequently made by Native Americans at public meetings. Native Americans were concerned that the quality of the Columbia River had deteriorated and that the poor environmental conditions had affected the health and quality of fish they relied on for subsistence, ceremonial, religious, and commercial purposes. They also feared that eating contaminated fish might endanger the health of their children and future generations. Operations at the Hanford Site were listed as one of many causes of the deteriorating environment. Fisheries pathologists concluded that most of the external symptoms on fish were related to bacterial infection of gill net abrasions and pre-spawning trauma, and were not caused by pollution or contamination of the Columbia River. The pathologists also stated that consumption of the fish posed no threat to human consumers.
Date: September 1, 1994
Creator: Abernethy, C. S.
Object Type: Report
System: The UNT Digital Library
The role of catalyst precursor anions in coal gasification. Tenth quarterly report (open access)

The role of catalyst precursor anions in coal gasification. Tenth quarterly report

This project investigates the roles of various aqueous soluble catalyst precursors containing various anions, specifically acetate (CH{sub 3}COO{sup {minus}}), chloride (Cl{sup {minus}}), nitrate (NO{sub 3}{sup {minus}}), sulfate (SO{sub 4}{sup 2{minus}}) and carbonate (CO{sub 3}{sup 2{minus}}) on the surface electrical properties of coal and seeks to understand the effects of these salts on the adsorption, dispersion and activities of calcium and potassium. The current report discusses the reactivities the lignite derived char catalyzed by {approximately}0.05 - 0.07 %wt. potassium. The catalytic compounds used were potassium acetate, potassium carbonate, potassium chloride, potassium nitrate, and potassium sulfate. The initial concentration of each salt solution from which potassium was ion-exchanged onto the coal was 0.001 mol/L and the metal was ion-exchanged onto the coal at the approximate pHs of 2, 6 and 9. Although the potassium contents in the chars were similar ({approximately}0.05 - 0.07 %wt.), a wide spread of char reactivities were observed. Char gasification ranged from > 90 %wt. to < 20 %wt. At this time, no general correlation between char reactivities, catalyst type, catalyst precursor anions or catalyst loading pH is obvious. However, the data are currently being analyzed in terms of zeta potentials to determine the effect, if any, of …
Date: July 1, 1994
Creator: Abotsi, G. M. K.
Object Type: Report
System: The UNT Digital Library
Preliminary analysis of the ORNL Liquid Low-Level Waste system (open access)

Preliminary analysis of the ORNL Liquid Low-Level Waste system

The objective of this report is to summarize the status of the Liquid Low-Level Waste (LLLW) Systems Analysis project. The focus of this project has been to collect and tabulate data concerning the LLLW system, analyze the current LLLW system operation, and develop the information necessary for the development of long-term treatment options for the LLLW generated at ORNL. The data used in this report were collected through a survey of Oak Ridge National Laboratory (ORNL) literature, various letter reports, and a survey of all current LLLW generators. These data are also being compiled in a user friendly database for ORNL-wide distribution. The database will allow the quick retrieval of all information collected on the ORNL LLLW system and will greatly benefit any LLLW analysis effort. This report summarizes the results for the analyses performed to date on the LLLW system.
Date: August 1, 1994
Creator: Abraham, T. J.; DePaoli, S. M.; Robinson, S. M. & Walker, A. B.
Object Type: Report
System: The UNT Digital Library
Cryogenic systems for the HEB accelerator of the Superconducting Super Collider (open access)

Cryogenic systems for the HEB accelerator of the Superconducting Super Collider

This report discusses the following topics related to the Superconducting Super Collider: Cryogenic system -- general requirements; cryogenic system components; heat load budgets and refrigeration plant capacities; flow and thermal characteristics; process descriptions; cryogenic control instrumentation and value engineering trade-offs.
Date: July 1, 1994
Creator: Abramovich, S. & Yuecel, A.
Object Type: Report
System: The UNT Digital Library
Characterization plan for Hanford spent nuclear fuel (open access)

Characterization plan for Hanford spent nuclear fuel

Reprocessing of spent nuclear fuel (SNF) at the Hanford Site Plutonium-Uranium Extraction Plant (PUREX) was terminated in 1972. Since that time a significant quantity of N Reactor and Single-Pass Reactor SNF has been stored in the 100 Area K-East (KE) and K-West (KW) reactor basins. Approximately 80% of all US Department of Energy (DOE)-owned SNF resides at Hanford, the largest portion of which is in the water-filled KE and KW reactor basins. The basins were not designed for long-term storage of the SNF and it has become a priority to move the SNF to a more suitable location. As part of the project plan, SNF inventories will be chemically and physically characterized to provide information that will be used to resolve safety and technical issues for development of an environmentally benign and efficient extended interim storage and final disposition strategy for this defense production-reactor SNF.
Date: December 1, 1994
Creator: Abrefah, J.; Thornton, T. A.; Thomas, L. E.; Berting, F. M. & Marschman, S. C.
Object Type: Report
System: The UNT Digital Library
ARAC`s site workstation final design and deployment (open access)

ARAC`s site workstation final design and deployment

The Atmospheric Release Advisory Capability (ARAC) Center located at Lawrence Livermore National Laboratory, provides real-time estimates of the environmental consequences of accidental releases of radioactivity or other hazardous materials into the atmosphere anywhere in the world. ARAC`s expertise includes integrating a suite of local, regional and global dispersion models into a highly automated system. Since 1979, on-site computers have provided the link between DOE and DOD facilities around the U.S. and the ARAC Center. Beginning in 1993, these facilities have been replacing their personal computers with UNIX workstations running ARAC`s Site Workstation Systems (SWS) software. The SWS consists of a collection of applications that help sites prepare for and respond to incidents involving an atmospheric release. The SWS can be used either as a real-time emergency-response tool or to make historical or hypothetical assessments of releases.
Date: August 1, 1994
Creator: Abriam, R. O. & Moore, R. M.
Object Type: Article
System: The UNT Digital Library