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The Baytown Sun (Baytown, Tex.), Vol. 80, No. 61, Ed. 1 Saturday, January 26, 2002
Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.
Date:
January 26, 2002
Creator:
Cash, Wanda Garner
Object Type:
Newspaper
System:
The Portal to Texas History
Accepting Mixed Waste as Alternate Feed Material for Processing and Disposal at a Licensed Uranium Mill
Certain categories of mixed wastes that contain recoverable amounts of natural uranium can be processed for the recovery of valuable uranium, alone or together with other metals, at licensed uranium mills, and the resulting tailings permanently disposed of as 11e.(2) byproduct material in the mill's tailings impoundment, as an alternative to treatment and/or direct disposal at a mixed waste disposal facility. This paper discusses the regulatory background applicable to hazardous wastes, mixed wastes and uranium mills and, in particular, NRC's Alternate Feed Guidance under which alternate feed materials that contain certain types of mixed wastes may be processed and disposed of at uranium mills. The paper discusses the way in which the Alternate Feed Guidance has been interpreted in the past with respect to processing mixed wastes and the significance of recent changes in NRC's interpretation of the Alternate Feed Guidance that sets the stage for a broader range of mixed waste materials to be processed as alternate feed materials. The paper also reviews the le gal rationale and policy reasons why materials that would otherwise have to be treated and/or disposed of as mixed waste, at a mixed waste disposal facility, are exempt from RCRA when reprocessed as alternate …
Date:
February 26, 2002
Creator:
Frydenland, D. C.; Hochstein, R. F. & Thompson, A. J.
Object Type:
Article
System:
The UNT Digital Library
Adequacy of a Small Quantity Site RH-TRU Waste Program in Meeting Proposed WIPP Characterization Objectives
The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste prior to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP …
Date:
February 26, 2002
Creator:
Biedscheid, J.; Stahl, S.; Devarakonda, M.; Peters, K. & Eide, J.
Object Type:
Article
System:
The UNT Digital Library
Los Alamos National Laboratory Tritium Technology Deployments Large Scale Demonstration and Deployment Project
This paper describes the organization, planning and initial implementation of a DOE OST program to deploy proven, cost effective technologies into D&D programs throughout the complex. The primary intent is to accelerate closure of the projects thereby saving considerable funds and at the same time being protective of worker health and the environment. Most of the technologies in the ''toolkit'' for this program have been demonstrated at a DOE site as part of a Large Scale Demonstration and Deployment Project (LSDDP). The Mound Tritium D&D LSDDP served as the base program for the technologies being deployed in this project but other LSDDP demonstrated technologies or ready-for-use commercial technologies will also be considered. The project team will evaluate needs provided by site D&D project managers, match technologies against those needs and rank deployments using a criteria listing. After selecting deployments the project will purchase the equipment and provide a deployment engineer to facilitate the technology implementation. Other cost associated with the use of the technology will be borne by the site including operating staff, safety and health reviews etc. A cost and performance report will be prepared following the deployment to document the results.
Date:
February 26, 2002
Creator:
McFee, J.; Blauvelt, D.; Stallings, E. & Willms, S.
Object Type:
Article
System:
The UNT Digital Library
ALARA Controls and the Radiological Lessons Learned During the Uranium Fuel Removal Projects at the Molten Salt Reactor Experiment
The removal of uranium-233 (233 U) from the auxiliary charcoal bed (ACB) of the Molten Salt Reactor Experiment (MSRE), performed from January through May 2001, created both unique radiological challenges and widely-applicable lessons learned. In addition to the criticality concerns and alpha contamination, 233U has an associated intense gamma photon from the cocontaminant uranium-232 (232U) decaying to thallium-208 (208Tl). Therefore, rigorous contamination controls and significant shielding were implemented. Extensive, timed mock-up training was also imperative to minimize individual and collective personnel exposures. Back-up shielding and containment techniques (that had been previously developed for defense in depth) were used successfully to control significant, changed conditions. Additional controls were placed on tests and on recovery designs to assure a higher level of safety throughout the removal operations. This paper delineates the manner in which each difficulty was solved, while relating the relevance of the results and the methodology to other projects with high dose-rate, highly-contaminated ionizing radiation hazards. Because of the distinctive features of and current interest in molten salt technology, a brief overview is provided. Also presented is the detailed, practical application of radiological controls integrated into, rather than added after, each evolution of the project--thus demonstrating the broad-based benefits of …
Date:
February 26, 2002
Creator:
Gilliam, B. J.; Chapman, J. A. & Jugan, M. R.
Object Type:
Article
System:
The UNT Digital Library
An Alternative to Performing Remote-Handled Transuranic Waste Container Headspace Gas Sampling and Analysis
The Waste Isolation Pilot Plant (WIPP) is operating under a Resource Conservation and Recovery Act (RCRA) Hazardous Waste Facility Permit (HWFP) for contact-handled (CH) transuranic (TRU) waste. The HWFP contains limitations on allowable emissions from waste disposed in the underground. This environmental performance standard imposed on the WIPP consists of limiting volatile organic compound (VOC) emissions from emplaced waste to ensure protection of human health and the environment. The standard is currently met by tracking individual waste container headspace gas concentrations, which are determined by headspace gas sampling and analysis of CH TRU waste containers. The WIPP is seeking a HWFP modification to allow the disposal of remote-handled (RH) TRU waste. Because RH TRU waste is limited to approximately 5% of the waste volume and is emplaced in the disposal room walls, it is possible to bound the potential RH TRU waste contribution to VOC emissions using conservative upper bounds. These conservative upper bounds were developed as an alternative to RH TRU waste canister headspace gas sampling and analysis. The methodology used to perform the calculations used to evaluate VOC emissions from emplaced RH TRU waste canisters applied the same equations as those used to evaluate VOC emissions in the …
Date:
February 26, 2002
Creator:
Spangler, L. R.; Djordjevic, S. M.; Kehrman, R. F. & Most, W. A.
Object Type:
Article
System:
The UNT Digital Library
Altus Times (Altus, Okla.), Vol. 103, No. 309, Ed. 1 Tuesday, February 26, 2002
Daily newspaper from Altus, Oklahoma that includes local, state, and national news along with advertising.
Date:
February 26, 2002
Creator:
Bush, Michael
Object Type:
Newspaper
System:
The Gateway to Oklahoma History
Anomalies in Proposed Regulations for the Release of Redundant Material from Nuclear and Non-nuclear Industries
Now that increasing numbers of nuclear power stations are reaching the end of their commercially useful lives, the management of the large quantities of very low level radioactive material that arises during their decommissioning has become a major subject of discussion, with very significant economic implications. Much of this material can, in an environmentally advantageous manner, be recycled for reuse without radiological restrictions. Much larger quantities--2-3 orders of magnitude larger--of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertilizer, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of T ENORM, specially the activity levels and quantities arising in so many nonnuclear industries. The first reaction of international organizations seems to have been to propose ''double'' standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to a hundred times more liberal criteria for the release/exemption of TENORM from the as …
Date:
February 26, 2002
Creator:
Menon, S.
Object Type:
Article
System:
The UNT Digital Library
Application of Archimedes Filter for Reduction of Hanford HLW
Archimedes Technology Group, Inc., is developing a plasma mass separator called the Archimedes Filter that separates waste oxide mixtures ion by ion into two mass groups: light and heavy. For the first time, it is feasible to separate large amounts of material atom by atom in a single pass device. Although vacuum ion based electromagnetic separations have been around for many decades, they have traditionally depended on ion beam manipulation. Neutral plasma devices, on the other hand, are much easier, less costly, and permit several orders of magnitude greater throughput. The Filter has many potential applications in areas where separation of species is otherwise difficult or expensive. In particular, radioactive waste sludges at Hanford have been a particularly difficult issue for pretreatment and immobilization. Over 75% of Hanford HLW oxide mass (excluding water, carbon, and nitrogen) has mass less than 59 g/mol. On the other hand, 99.9% of radionuclide activity has mass greater than 89 g/mol. Therefore, Filter mass separation tuned to this cutoff would have a dramatic effect on the amount of IHLW produced--in fact IHLW would be reduced by a factor of at least four. The Archimedes Filter is a brand new tool for the separations specialist's toolbox. …
Date:
February 26, 2002
Creator:
Gilleland, J.; Agnew, S.; Cluggish, B.; Freeman, R.; Miller, R.; Putvinski, S. et al.
Object Type:
Article
System:
The UNT Digital Library
Application of seismic isolation to the STAR-LM reactor.
None
Date:
February 26, 2002
Creator:
Kulak, R.F. & Yoo, B.
Object Type:
Article
System:
The UNT Digital Library
Assessment of Hard-to-Detect Radionuclide Levels in Decommissioning Waste From the Bohunice NPP-A1, Slovakia, for Clearance and Disposal Purposes
For assessments of hard-to-detect radionuclides (HD-RN) contents in various type of radwastes at the NPP-A1, available empirical data referenced to 137Cs (actinides, 90Sr, 99Tc, 63Ni, 14C) and the theoretical assessment for the remaining HD-RN using calculated RN inventory and a simple model with effective relative (137Cs) spent fuel release fractions was applied. The analytical data of extended radiochemical analysis for the existing available operational radwaste forms have been reviewed for this purpose. 137Cs, 90Sr and 241Am were set up as release markers for partial spent fuel release groups of HD-RNs within which the total fractions of HD-RN released to the operational radwastes were assumed to be constant. It was shown by the assessment carried out that 137Cs and HD-RNs 129I, 99Tc, and partly 79Se and 14C are the main contributors to the disposal dose limit for the radioactive concentrate at NPP A-1. In the case of the radioactive sludge from the operational radwaste system the role of predominant dose contributors belongs to actinides 239,240Pu and 241Am. In the case of clearance of radioactive material from the NPP-A1 site, only the reference radionuclide, 137Cs was predicted to be the most dominant dose contributor. In all of these cases the estimated contributions …
Date:
February 26, 2002
Creator:
Slavik, O.; Moravek, J. & Stubna, M.
Object Type:
Article
System:
The UNT Digital Library
Automotive Underhood Thermal Management Analysis Using 3-D Coupled Thermal-Hydrodynamic Computer Models: Thermal Radiation Modeling
The goal of the radiation modeling effort was to develop and implement a radiation algorithm that is fast and accurate for the underhood environment. As part of this CRADA, a net-radiation model was chosen to simulate radiative heat transfer in an underhood of a car. The assumptions (diffuse-gray and uniform radiative properties in each element) reduce the problem tremendously and all the view factors for radiation thermal calculations can be calculated once and for all at the beginning of the simulation. The cost for online integration of heat exchanges due to radiation is found to be less than 15% of the baseline CHAD code and thus very manageable. The off-line view factor calculation is constructed to be very modular and has been completely integrated to read CHAD grid files and the output from this code can be read into the latest version of CHAD. Further integration has to be performed to accomplish the same with STAR-CD. The main outcome of this effort is to obtain a highly scalable and portable simulation capability to model view factors for underhood environment (for e.g. a view factor calculation which took 14 hours on a single processor only took 14 minutes on 64 processors). …
Date:
February 26, 2002
Creator:
Pannala, S.; D'Azevedo, E. & Zacharia, T.
Object Type:
Report
System:
The UNT Digital Library
Autonomous load following and operational aspects of the STAR-LM HLMC natural convection reactor.
None
Date:
February 26, 2002
Creator:
Sienicki, J. J. & Petkov, P. V.
Object Type:
Article
System:
The UNT Digital Library
AVS: Experimental Tests of a New Process to Inductively Vitrify HLW Inside the Final Disposal Containers at Very High Waste Loadings
The design and performance capabilities of the Advanced Vitrification System (AVS) are described, together with the results of experimental tests. The AVS is an in-can melting system in which high-level waste (HLW) is vitrified directly inside the final disposal container. The AVS container, or module, consists of an outer stainless steel canister and an alumina-lined, inner graphite crucible, which is thermally insulated from the outer stainless canister. The graphite crucible is inductively heated to very high temperatures (up to 1500 C) by an external low frequency (30 Hertz) alternating current (AC) transformer coil. The actively cooled outer stainless canister remains at near ambient temperature. The HLW/frit mixture is fed into the hot graphite crucible, where it is vitrified. After cooldown, the HLW/frit feed and off-gas pipes are disconnected from the top of the module, which is then sealed and readied for shipment or storage. All radioactively contaminated melter components inside the module are disposed of along with the vitrified waste. The graphite crucible also provides a geologically stable barrier for the vitrified product. The AVS potentially can double HLW loading over that obtained from Joule melters; lower vitrification costs by about half; reduce the number of disposal canisters required by …
Date:
February 26, 2002
Creator:
Powell, J.; Reich, M.; Jordan, J.; Ventre, L.; Barletta, R.; Manowitz, B. et al.
Object Type:
Article
System:
The UNT Digital Library
Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium
Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs …
Date:
February 26, 2002
Creator:
Gillas, D. L. & Chambers, B. K.
Object Type:
Article
System:
The UNT Digital Library
Basic Science Research to Support the Nuclear Materials Focus Area
The Department of Energy's (DOE's) Office of Environmental Management (EM) is responsible for managing more than 760,000 metric tons of nuclear material that is excess to the current DOE weapons program, as a result of shutdown of elements of the weapons program, mainly during the 1990s. EMowned excess nuclear material comprises a variety of material types, including uranium, plutonium, other actinides and other radioactive elements in numerous forms, all of which must be stabilized for storage and ultimate disposition. Much of this quantity has been in storage for many years. Shutdown of DOE sites and facilities requires removal of nuclear material and consolidation at other sites, and may be delayed by the lack of available technology. Within EM, the Office of Science and Technology (OST) is dedicated to providing timely, relevant technology to accelerate completion and reduce cleanup cost of the DOE environmental legacy. OST is organized around five focus areas, addressing crucial areas of end-user-defined technology need. The Focus Areas regularly identify potential technical solutions for which basic scientific research is needed to determine if the technical solution can be developed and deployed. To achieve a portfolio of projects that is balanced between near-term priorities driven by programmatic risks …
Date:
February 26, 2002
Creator:
Chipman, N. A.; Castle, P. M.; Boak, J. M. & Eller, P. G.
Object Type:
Article
System:
The UNT Digital Library
The Baytown Sun (Baytown, Tex.), Vol. 80, No. 92, Ed. 1 Tuesday, February 26, 2002
Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.
Date:
February 26, 2002
Creator:
Cash, Wanda Garner
Object Type:
Newspaper
System:
The Portal to Texas History
A Benchmarking Analysis for Five Radionuclide Vadose Zone Models (Chain, Multimed{_}DP, Fectuz, Hydrus, and Chain 2D) in Soil Screening Level Calculations
Five vadose zone models with different degrees of complexity (CHAIN, MULTIMED{_}DP, FECTUZ, HYDRUS, and CHAIN 2D) were selected for use in radionuclide soil screening level (SSL) calculations. A benchmarking analysis between the models was conducted for a radionuclide ({sup 99}Tc) release scenario at the Las Cruces Trench Site in New Mexico. Sensitivity of three model outputs to the input parameters were evaluated and compared among the models. The three outputs were peak contaminant concentrations, time to peak concentrations at the water table, and time to exceed the contaminants maximum critical level at a representative receptor well. Model parameters investigated include soil properties such as bulk density, water content, soil water retention parameters and hydraulic conductivity. Chemical properties examined include distribution coefficient, radionuclide half-life, dispersion coefficient, and molecular diffusion. Other soil characteristics, such as recharge rate, also were examined. Model sensitivity was quantified in the form of sensitivity and relative sensitivity coefficients. Relative sensitivities were used to compare the sensitivities of different parameters. The analysis indicates that soil water content, recharge rate, saturated soil water content, and soil retention parameter, {beta}, have a great influence on model outputs. In general, the results of sensitivities and relative sensitivities using five models are …
Date:
February 26, 2002
Creator:
Chen, J-S.; Drake, R.; Lin, Z. & Jewett, D. G.
Object Type:
Article
System:
The UNT Digital Library
Biosphere Modeling and Analyses in Support of Total System Performance Assessment
The Nuclear Waste Policy Act of 1982 established the obligations of and the relationship between the U.S. Environmental Protection Agency (EPA), the U.S. Nuclear Regulatory Commission (NRC), and the U.S. Department of Energy (DOE) for the management and disposal of high-level radioactive wastes. In 1985, the EPA promulgated regulations that included a definition of performance assessment that did not consider potential dose to a member of the general public. This definition would influence the scope of activities conducted by DOE in support of the total system performance assessment program until 1995. The release of a National Academy of Sciences (NAS) report on the technical basis for a Yucca Mountain-specific standard provided the impetus for the DOE to initiate activities that would consider the attributes of the biosphere, i.e. that portion of the earth where living things, including man, exist and interact with the environment around them. The evolution of NRC and EPA Yucca Mountain-specific regulations, originally proposed in 1999, was critical to the development and integration of biosphere modeling and analyses into the total system performance assessment program. These proposed regulations initially differed in the conceptual representation of the receptor of interest to be considered in assessing performance. The publication …
Date:
February 26, 2002
Creator:
Tappen, J. J.; Wasiolek, M. A.; Wu, D. W.; Schmitt, J. F. & Smith, A. J.
Object Type:
Article
System:
The UNT Digital Library
The Boerne Star (Boerne, Tex.), Vol. 97, No. 17, Ed. 1 Tuesday, February 26, 2002
Semiweekly newspaper from Boerne, Texas that includes local, state, and national news along with advertising.
Date:
February 26, 2002
Creator:
Keasling, Edna & Mahoney, Kent
Object Type:
Newspaper
System:
The Portal to Texas History
Brady Standard-Herald and Heart O' Texas News (Brady, Tex.), Ed. 1 Tuesday, February 26, 2002
Semiweekly newspaper from Brady, Texas that includes local, state, and national news along with advertising.
Date:
February 26, 2002
Creator:
Stewart, James E.
Object Type:
Newspaper
System:
The Portal to Texas History
Building 7602 Decontamination and Decommissioning for Reuse by Spallation Neutron Source
Building 7602 at the Oak Ridge National Laboratory (ORNL) was constructed in 1963 as a Reactor Service Building for the Experimental Gas-Cooled Reactor; the reactor was never fueled or operated, and the project was terminated in 1965. Significant building modifications were performed during the late 1970s and early 1980s. Beginning in 1984, separation processes and equipment development and testing were initiated for the Consolidated Fuel Reprocessing Program (CFRP). The principal materials used in the processes were depleted and natural uranium, nitric acid, and organic solvents. CFRP operations continued until 1994 when the program was discontinued and the facility declared surplus to the U.S. Department of Energy (DOE). Systems and equipment were shut down; feed and waste materials were removed; and process fluids, chemicals, and uranium were drained and flushed from systems. This paper will present an overview of the Building 7602 D&D activities, final radiological survey , facility modifications, and project interfaces.
Date:
February 26, 2002
Creator:
Brill, A.; Berger, J.; Kelsey, A. & Plummer, K.
Object Type:
Article
System:
The UNT Digital Library
Closing Rocky Flats by 2006
Safely accelerating the closure of Rocky Flats to 2006 is a goal shared by many: the State of Colorado, the communities surrounding the site, the U.S. Congress, the Department of Energy, Kaiser-Hill and its team of subcontractors, the site's employees, and taxpayers across the country. On June 30, 2000, Kaiser-Hill (KH) submitted to the Department of Energy (DOE), KH's plan to achieve closure of Rocky Flats by December 15, 2006, for a remaining cost of $3.96 billion (February 1, 2000, to December 15, 2006). The Closure Project Baseline (CPB) is the detailed project plan for accomplishing this ambitious closure goal. This paper will provide a status report on the progress being made toward the closure goal. This paper will: provide a summary of the closure contract completion criteria; give the current cost and schedule variance of the project and the status of key activities; detail important accomplishments of the past year; and discuss the challenges ahead.
Date:
February 26, 2002
Creator:
Tuor, N. R. & Schubert, A. L.
Object Type:
Article
System:
The UNT Digital Library
COGEMA Experience on Retrieving and Automatically Remote Cutting Large Metallic Structures Using Special Saw During Nuclear Decommissioning Operations
Used spent fuel baskets have been stored in the La Hague North-West concrete-lined pits until decommissioning. In 1998, COGEMA decided to retrieve, cut and condition these spent fuel baskets. This paper describes the experience gained, since the start up of this operation in 1999, discusses resulting dosimetry and waste produced, during retrieving and remotely cutting of LL activity large metallic structures. This process result in significantly lower exposures to workers in the D and D operations. In addition the work was carried out in an environmentally safe manner with reasonable financial costs.
Date:
February 26, 2002
Creator:
Bodin, F. & Barandas, C.
Object Type:
Article
System:
The UNT Digital Library