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Development of a Fuel Containing Material Removal and Waste Management Strategy for the Chernobyl Unit 4 Shelter (open access)

Development of a Fuel Containing Material Removal and Waste Management Strategy for the Chernobyl Unit 4 Shelter

A study was performed to develop a strategy for the removal of fuel-containing material (FCM) from the Chernobyl Unit 4 Shelter and for the related waste management. This study was performed during Phase 1 of the Shelter Implementation Plan (SIP) and was funded by the Chernobyl Shelter Fund. The main objective for Phase 2 of the SIP is to stabilize the Shelter and to construct a New Confinement (NC) by the year 2007. In addition, the SIP includes studies on the strategy and on the conceptual design implications of the removal of FCM from the Shelter. This is considered essential for the ultimate goal, the transformation of the Shelter into an environmentally safe system.
Date: February 27, 2002
Creator: Tokarevsky, V. V.; Shibetsky, Y. A.; Leister, P.; Davison, W. R.; Follin, J. F.; McNair, J. et al.
Object Type: Article
System: The UNT Digital Library
Mixed Waste Treatment Cost Analysis for a Range of GeoMelt Vitrification Process Configurations (open access)

Mixed Waste Treatment Cost Analysis for a Range of GeoMelt Vitrification Process Configurations

GeoMelt is a batch vitrification process used for contaminated site remediation and waste treatment. GeoMelt can be applied in several different configurations ranging from deep subsurface in situ treatment to aboveground batch plants. The process has been successfully used to treat a wide range of contaminated wastes and debris including: mixed low-level radioactive wastes; mixed transuranic wastes; polychlorinated biphenyls; pesticides; dioxins; and a range of heavy metals. Hypothetical cost estimates for the treatment of mixed low-level radioactive waste were prepared for the GeoMelt subsurface planar and in-container vitrification methods. The subsurface planar method involves in situ treatment and the in-container vitrification method involves treatment in an aboveground batch plant. The projected costs for the subsurface planar method range from $355-$461 per ton. These costs equate to 18-20 cents per pound. The projected cost for the in-container method is $1585 per ton. This cost equates to 80 cents per pound. These treatment costs are ten or more times lower than the treatment costs for alternative mixed waste treatment technologies according to a 1996 study by the US Department of Energy.
Date: February 27, 2002
Creator: Thompson, L. E.
Object Type: Article
System: The UNT Digital Library
United States Department of Energy Nuclear Materials Stewardship (open access)

United States Department of Energy Nuclear Materials Stewardship

The Department of Energy launched the Nuclear Materials Stewardship Initiative in January 2000 to accelerate the work of achieving integration and cutting long-term costs associated with the management of the Department's nuclear materials, with the principal focus on excess materials. Management of nuclear materials is a fundamental and enduring responsibility that is essential to meeting the Department's national security, nonproliferation, energy, science, and environmental missions into the distant future. The effective management of nuclear materials is important for a set of reasons: (1) some materials are vital to our national defense; (2) the materials pose physical and security risks; (3) managing them is costly; and (4) costs are likely to extend well into the future. The Department currently manages nuclear materials under eight programs, with offices in 36 different locations. Through the Nuclear Materials Stewardship Initiative, progress was during calendar year 20 00 in achieving better coordination and integration of nuclear materials management responsibilities and in evaluating opportunities to further coordinate and integrate cross-program responsibilities for the treatment, storage, and disposition of excess nuclear materials. During CY 2001 the Departmental approach to nuclear materials stewardship changed consistent with the business processes followed by the new administration. This paper reports on …
Date: February 27, 2002
Creator: Newton, J. W.
Object Type: Article
System: The UNT Digital Library
Emery Biomass Gasification Power System: Final Report (open access)

Emery Biomass Gasification Power System: Final Report

Emery Recycling Corporation (now Emery Energy Company, LLC) evaluated the technical and economical feasibility of the Emery Biomass Gasification Power System (EBGPS). The gasifier technology is owned and being developed by Emery. The Emery Gasifier for this project was an oxygen-blown, pressurized, non-slagging gasification process that novelly integrates both fixed-bed and entrained-flow gasification processes into a single vessel. This unique internal geometry of the gasifier vessel will allow for tar and oil destruction within the gasifier. Additionally, the use of novel syngas cleaning processes using sorbents is proposed with the potential to displace traditional amine-based and other syngas cleaning processes. The work scope within this project included: one-dimensional gasifier modeling, overall plant process modeling (ASPEN), feedstock assessment, additional analyses on the proposed syngas cleaning process, plant cost estimating, and, market analysis to determine overall feasibility and applicability of the technology for further development and commercial deployment opportunities. Additionally, the project included the development of a detailed technology development roadmap necessary to commercialize the Emery Gasification technology. Process modeling was used to evaluate both combined cycle and solid oxide fuel cell power configurations. Ten (10) cases were evaluated in an ASPEN model wherein nine (9) cases were IGCC configurations with fuel-to-electricity …
Date: November 27, 2002
Creator: Phillips, Benjamin; Hassett, Scott & Gatley, Harry
Object Type: Report
System: The UNT Digital Library
High Level Waste Tank Closure Project at the Idaho National Engineering and Environmental Laboratory (open access)

High Level Waste Tank Closure Project at the Idaho National Engineering and Environmental Laboratory

The Department of Energy, Idaho Operations Office (DOE-ID) is making preparations to close two underground high-level waste (HLW) storage tanks at the Idaho National Engineering and Environmental Laboratory (INEEL) to meet Resource Conservation and Recovery Act (RCRA) regulations and Department of Energy orders. Closure of these two tanks is scheduled for 2004 as the first phase in closure of the eleven 300,000 gallon tanks currently in service at the Idaho Nuclear Technology and Engineering Center (INTEC). The INTEC Tank Farm Facility (TFF) Closure sequence consists of multiple steps to be accomplished through the existing tank riser access points. Currently, the tank risers contain steam and process waste lines associated with the steam jets, corrosion coupons, and liquid level indicators. As necessary, this equipment will be removed from the risers to allow adequate space for closure equipment and activities.
Date: February 27, 2002
Creator: Wessman, D. L. & Quigley, K. D.
Object Type: Article
System: The UNT Digital Library
More modular invariant anomalous U(1) breaking (open access)

More modular invariant anomalous U(1) breaking

We consider the case of several scalar fields, charged under a number of U(1) factors, acquiring vacuum expectation values due to anomalous U(1). We demonstrate how to make redefinitions at the superfield level in order to account for tree-level exchange of vector supermultiplets in the effective supergravity theory of the light fields in the supersymmetric vacuum phase. Our approach builds up on previous results that we obtained in a more elementary case. We find that the modular weights of light fields are typically shifted from their original values, allowing an interpretation in terms of the preservation of modular invariance in the effective theory. We address various subtleties in defining unitary gauge that are associated with the noncanonical Kahler potential of modular invariant supergravity, the vacuum degeneracy, and the role of the dilaton field. We discuss the effective superpotential for the light fields and note how proton decay operators may be obtained when the heavy fields are integrated out of the theory at the tree-level. We also address how our formalism may be extended to describe the generalized Green-Schwarz mechanism for multiple anomalous U(1)'s that occur in four-dimensional Type I and Type IIB string constructions.
Date: June 27, 2002
Creator: Gaillard, Mary K. & Giedt, Joel
Object Type: Article
System: The UNT Digital Library
The Decommissioning of the Trino Nuclear Power Plant (open access)

The Decommissioning of the Trino Nuclear Power Plant

Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by …
Date: February 27, 2002
Creator: Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P. & Watson, B.
Object Type: Article
System: The UNT Digital Library
Current Status of the United Kingdom Programme for Long-Term Radioactive Waste Management (open access)

Current Status of the United Kingdom Programme for Long-Term Radioactive Waste Management

In 1997, the UK programme for the deep disposal of radioactive waste was ''stopped dead in its tracks'' with the refusal by the Secretary of State for the Environment to allow Nirex to go ahead with its plans for an underground Rock Characterisation Facility at Sellafield in north-west England. Since that time a House of Lords' Select Committee has held an inquiry into what went wrong and what the way ahead should be. In addition, Nirex and the nuclear industry players have also been analyzing the past with a view to learning from the experience in taking things forward. In Nirex's view this is essentially an ethical issue; the waste exists and we should deal with it in this generation. Three areas need to be better addressed if a successful program of management of the nation's radioactive waste is to be achieved: the process of how policy development and implementation can be achieved; the structure of the nuclear industry and its relationship to the waste management organization; and the behavior of the players in their interaction with stakeholders. All three are underpinned by the need for transparency. In recognition that developing a policy for managing radioactive waste has to be …
Date: February 27, 2002
Creator: Murray, C. H.; Hooper, A. J. & Mathieson, J.
Object Type: Article
System: The UNT Digital Library
In-Situ Grouting Treatability Study for the Idaho National Engineering and Environmental Laboratory Subsurface Disposal Area-Transuranic Pits and Trenches (open access)

In-Situ Grouting Treatability Study for the Idaho National Engineering and Environmental Laboratory Subsurface Disposal Area-Transuranic Pits and Trenches

At the Idaho National Engineering and Environmental Laboratory (INEEL), a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) treatability study is being performed to examine the technology of in situ grouting for final in situ disposal of buried mixed transuranic (TRU) waste. At the INEEL, there is over 56,000 cubic meters of waste commingled with a similar amount of soil in a shallow (3-5 m) land burial referred to as Waste Area Group 7-13/14. Since this buried waste has been declared on the National Priorities List under CERCLA, it is being managed as a superfund site. Under CERCLA, options for this waste include capping and continued monitoring, retrieval and ex situ management of the retrieved waste, in situ stabilization by vitrification or grouting, in situ thermal dissorption, or some combination of these options. In situ grouting involves injecting grout at high pressures (400 bars) directly into the waste to create a solid monolith. The in situ grouting process is expected to both stabilize the waste against subsidence and provide containment against migration of waste to the Snake River Plain Aquifer lying 150-200 m below the waste. The treatability study involves bench testing, implementability testing, and field testing. The bench testing …
Date: February 27, 2002
Creator: Loomis, G. G.; Jessmore, J. J.; Sehn, A. L. & Miller, C. M.
Object Type: Article
System: The UNT Digital Library
U.S. Department of Energy's Siting Guidelines at 10 CFR 963 (open access)

U.S. Department of Energy's Siting Guidelines at 10 CFR 963

The U.S. Department of Energy (DOE) has amended the policies under the Nuclear Waste Policy Act of 1982 for evaluating the suitability of Yucca Mountain, Nevada, as a site for development of a nuclear waste repository. The final rule at Title 10, Part 963 of the Code of Federal Regulations (10 CFR Part 963) focuses on the criteria and methodology to be used for evaluating relevant geological and other related aspects of the Yucca Mountain site. Consistent with the long standing policy to conform the DOE suitability guidelines for its nuclear waste repository program to licensing regulations of the U.S. Nuclear Regulatory Commission (NRC), the DOE's criteria and methodology are consistent with the NRC's recently final regulations for licensing a nuclear waste repository at Yucca Mountain.
Date: February 27, 2002
Creator: Kouts, C. A.; Murray, R. C.; Voegele, M. D. & Boyle, W. L.
Object Type: Article
System: The UNT Digital Library
Tube-wave suppression in single-well seismic acquisition (open access)

Tube-wave suppression in single-well seismic acquisition

None
Date: February 27, 2002
Creator: Daley, Thomas M.; Gritto, Roland; Majer, Ernest L. & West, Phillip
Object Type: Article
System: The UNT Digital Library
Rancho Seco-Planning for Large Components (open access)

Rancho Seco-Planning for Large Components

The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of Safestor to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful work to date, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and the Auxiliary Building and should be completed by mid 2003. The Spent Fuel is currently being moved to dry storage in an onsite ISFSI, with completion scheduled for late 2002. The personnel resources on site are currently assigned to support both the dry fuel project and the dismantlement of the facility. Once fuel movement is complete more resources will be provided for dismantlement. Characterization of major components other than the vessel is complete and planning for their removal is in progress with various cut-up and/or shipping options being evaluated. Planning for the vessel and …
Date: February 27, 2002
Creator: Gardiner, Dennis E.; Newey, Joel M & Snyder, Michael W.
Object Type: Article
System: The UNT Digital Library
St. Louis FUSRAP-A Strategy for Success (open access)

St. Louis FUSRAP-A Strategy for Success

In October 1997, Congress transferred the Formerly Utilized Sites Remedial Action Program (FUSRAP) from the Department of Energy (DOE) to the United States Army Corps of Engineers (USACE). FUSRAP addresses contamination generated by activities of the Manhattan Engineering District and the Atomic Energy Commission during the 1940's and 50's in support of the nation's nuclear weapons development program. The USACE Operation Order for FUSRAP gave responsibility for remediation of five sites in Missouri and Illinois to the USACESt. Louis District. The principal site is the St. Louis Airport Site (SLAPS), which involves the removal, transportation, disposal, and restoration of approximately 28 acres and 245,000 bank cubic yards (bcy) of contaminated soils. This paper will focus on the progress and achievements in removal action efficiencies of the SLAPS team. This team consists primarily of the USACE and Stone & Webster, Incorporated.
Date: February 27, 2002
Creator: Lyerla, M.; Fox, B.; Chinnock, J.; Haase, A.; Wojinski, S.; Bretz, M. et al.
Object Type: Article
System: The UNT Digital Library
Long Term Stewardship Challenges at the St. Louis District FUSRAP Sites (open access)

Long Term Stewardship Challenges at the St. Louis District FUSRAP Sites

Non-Federally owned radioactively contaminated sites in St. Louis, Missouri are currently being remediated by the St. Louis District Corps of Engineers under the Formerly Utilized Sites Remedial Action Program (FUSRAP). When FUSRAP remediation is complete, inaccessible soils which have levels of contamination greater than unrestricted use standards, will remain. The purpose of this paper is to document the initial challenges facing the project team during its development of the Long Term Stewardship plan for the management of these soils. These soils are located under buildings, roads, railroads and bridges. The Long Term Stewardship plan for the majority of the sites is being developed simultaneously with the remedy selection process. A living document, it will ultimately document the remedial action end state and location of inaccessible soils and implement the plan for ensuring these soils are not a threat to human health and the environment. Although these soils are protective in their current configuration, at some point in time, when activities such as maintenance, utility or property improvement occur, the soils will become accessible and need to be addressed by the federal government. Up until that point in time they will need to be effectively managed to ensure they remain protective. …
Date: February 27, 2002
Creator: Dell'Orco, L. & Chambers, D.
Object Type: Article
System: The UNT Digital Library
Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition (open access)

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection …
Date: February 27, 2002
Creator: Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W. et al.
Object Type: Article
System: The UNT Digital Library
Intermodal Transportation, USACE Style (open access)

Intermodal Transportation, USACE Style

The US Army Corps of Engineers (USACE) has developed project management techniques with a proven track record for safe and successful results for constructing large scale and massive projects such as improving our nations water transportation systems, flood control, bridges and dams. Applying many of these techniques to the Formerly Utilized Sites Remedial Action Program (FUSRAP) managed by USACE to remediate the environment is achieving the same safe and successful results as their construction projects. This paper examines the additional economics and improved safety results of using intermodal containers and a combination of rail and truck transportation conveyances to transport the contaminated soil and debris from the Linde FUSRAP site, located in Tonawanda, New York.
Date: February 27, 2002
Creator: Grumski, K. M. & Coutts, P. W.
Object Type: Article
System: The UNT Digital Library
Conditioning of BWR Control - Elements Using the New MOSAIK 80T/SWR-SE Cask - Concept (open access)

Conditioning of BWR Control - Elements Using the New MOSAIK 80T/SWR-SE Cask - Concept

During the operation of Boiling Water Reactors, Control - Elements are used to control the neutron flux inside the reactor vessel. After the end of the lifetime, the Control - Elements are usually stored in the fuel - elements - pool of the reactor. Up to now, in Germany no conditioning of Control - Elements has been done in a BWR under operation.
Date: February 27, 2002
Creator: Oldiges, O.; Blenski, H.-J.; Engelage, H.; Behrens, W.; Majunke, J.; Schwarz, W. et al.
Object Type: Article
System: The UNT Digital Library
Evaluation of Management Routes for the Paldiski Sarcophagi (open access)

Evaluation of Management Routes for the Paldiski Sarcophagi

The necessity to develop the submarine fleet in Russia required constructing a special training base for the training of submarine crews. To this purpose two prototypes of nuclear power units, close analogous to those fitting out nuclear submarines were constructed and commissioned in the sixties on the Navy training centre's base located in Paldiski (Pakri peninsula, Estonia). In 1994, nuclear fuel was discharged from the reactors and transported to Russia while the reactors themselves were prepared for prolonged storage, prior to transfer of the Paldiski facilities to the ownership of the Estonian Republic. The Paldiski facilities are currently being dismantled with the exception of two sarcophagi made of concrete that are housing the two reactor compartments. The question of the future management of both sarcophagi is a key-issue in the cleaning up of the whole Paldiski site. Actually, three basic questions should answered: when should dismantling operations occur, how this should be done, and what could be the corresponding cost. Within the context of enlargement of the European Union, the Commission services (first Directorate-General for Environment and then Directorate-General for Enlargement) decided to support Estonia to respond to these three questions through a study contract that was awarded in 1999 …
Date: February 27, 2002
Creator: Antonel, L.; Robin, B.; Miller, J. W.; Putnik, H. & Simanovski, Y.
Object Type: Article
System: The UNT Digital Library
Nonlinear dynamics in flow through unsaturated fractured-porous media: Status and perspectives (open access)

Nonlinear dynamics in flow through unsaturated fractured-porous media: Status and perspectives

The need has long been recognized to improve predictions of flow and transport in partially saturated heterogeneous soils and fractured rock of the vadose zone for many practical applications, such as remediation of contaminated sites, nuclear waste disposal in geological formations, and climate predictions. Until recently, flow and transport processes in heterogeneous subsurface media with oscillating irregularities were assumed to be random and were not analyzed using methods of nonlinear dynamics. The goals of this paper are to review the theoretical concepts, present the results, and provide perspectives on investigations of flow and transport in unsaturated heterogeneous soils and fractured rock, using the methods of nonlinear dynamics and deterministic chaos. The results of laboratory and field investigations indicate that the nonlinear dynamics of flow and transport processes in unsaturated soils and fractured rocks arise from the dynamic feedback and competition between various nonlinear physical processes along with complex geometry of flow paths. Although direct measurements of variables characterizing the individual flow processes are not technically feasible, their cumulative effect can be characterized by analyzing time series data using the models and methods of nonlinear dynamics and chaos. Identifying flow through soil or rock as a nonlinear dynamical system is important …
Date: November 27, 2002
Creator: Faybishenko, Boris
Object Type: Article
System: The UNT Digital Library
Demonstrating and Deploying Private Sector Technologies at DOE Sites - Issues to be Overcome (open access)

Demonstrating and Deploying Private Sector Technologies at DOE Sites - Issues to be Overcome

The Department of Energy (DOE), Office of Environmental Management (EM) continues to pursue cost-effective, environmental cleanup of the weapons complex sites with a concomitant emphasis on deployment of innovative technologies as a means to this end. The EM Office of Science and Technology (OST) pursues a strategy that entails identification of technologies that have potential applications throughout the DOE complex: at multiple DOE sites and at multiple facilities on those sites. It further encourages a competitive procurement process for the various applications entailed in the remediation of a given facility. These strategies require a competitive private-sector supplier base to help meet EM needs. OST supports technology development and deployment through investments in partnerships with private industry to enhance the acceptance of their technology products within the DOE market. Since 1992, OST and the National Energy Technology Laboratory (NETL) have supported the re search and development of technology products and services offered by the private sector. During this time, NETL has managed over 140 research and development projects involving industrial and university partners. These projects involve research in a broad range of EM related topics, including deactivation and decommissioning, characterization, monitoring, sensors, waste separation, groundwater remediation, robotics, and mixed waste treatment. …
Date: February 27, 2002
Creator: Bedick, R. C.
Object Type: Article
System: The UNT Digital Library
Remediation and Recycling of Linde FUSRAP Materials (open access)

Remediation and Recycling of Linde FUSRAP Materials

During World War II, the Manhattan Engineering District (MED) utilized facilities in the Buffalo, New York area to extract natural uranium from uranium-bearing ores. The Linde property is one of several properties within the Tonawanda, New York Formerly Utilized Sites Remedial Action Program (FUSRAP) site, which includes Linde, Ashland 1, Ashland 2, and Seaway. Union Carbide Corporation's Linde Division was placed under contract with the Manhattan Engineering District (MED) from 1942 to 1946 to extract uranium from seven different ore sources: four African pitchblende ores and three domestic ores. Over the years, erosion and weathering have spread contamination from the residuals handled and disposed of at Linde to adjacent soils. The U.S. Department of Energy (DOE) and the U.S. Environmental Protection Agency (EPA) negotiated a Federal Facilities Agreement (FFA) governing remediation of the Linde property. In Fiscal Year (FY) 1998, Congress transferred cleanup management responsibility for the sites in the FUSRAP program, including the Linde Site, from the DOE to the U.S. Army Corps of Engineers (USACE), with the charge to commence cleanup promptly. All actions by the USACE at the Linde Site are being conducted subject to the administrative, procedural, and regulatory provisions of the Comprehensive Environmental Response Compensation …
Date: February 27, 2002
Creator: Coutts, Peter W.; Franz, John P. & Rehmann, Michelle R.
Object Type: Article
System: The UNT Digital Library
The Gunite Tanks Remediation Project at Oak Ridge National Laboratory; Successful Integration & Deployment of Technologies Results in Remediated Underground Storage Tanks (open access)

The Gunite Tanks Remediation Project at Oak Ridge National Laboratory; Successful Integration & Deployment of Technologies Results in Remediated Underground Storage Tanks

This paper presents an overview of the underground technologies deployed during the cleanup of nine large underground storage tanks (USTs) that contained residual radioactive sludge, liquid low-level waste (LLLW), and other debris. The Gunite Tanks Remediation Project at Oak Ridge National Laboratory (ORNL) was successfully completed in 2001, ending with the stabilization of the USTs and the cleanup of the South Tank Farm. This U.S. Department of Energy (DOE) project was the first of its kind completed in the United States of America. The Project integrated robotic and remotely operated technologies into an effective tank waste retrieval system that safely retrieved more than 348 m3 (92,000 gal) of radioactive sludge and 3.15E+15 Bq (85,000 Ci) of radioactive contamination from the tanks. The Project successfully transferred over 2,385 m3 (630,000 gal) of waste slurry to ORNL's active tank waste management system. The project team avoided over $120 Million in costs and shortened the original baseline schedule by over 10 years. Completing the Gunite Tanks Remediation Project eliminated the risks posed by the aging USTs and the waste they contained, and avoid the $400,000 annual costs associated with maintaining and monitoring the tanks.
Date: February 27, 2002
Creator: Billingsley, K. & Bolling, D.
Object Type: Article
System: The UNT Digital Library
Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems (open access)

Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems

The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 …
Date: December 27, 2002
Creator: Bruemmer, Stephen M.; Andersen, Peter L. & Was, Gary
Object Type: Report
System: The UNT Digital Library
Concept for Dismantling the Reactor Vessel and the Biological Shield of the Compact Sodium-Cooled Nuclear Reactor Facility (KNK) (open access)

Concept for Dismantling the Reactor Vessel and the Biological Shield of the Compact Sodium-Cooled Nuclear Reactor Facility (KNK)

The Compact Sodium-cooled Nuclear Reactor Facility (KNK) was an experimental nuclear power plant of 20 MW electric power erected on the premises of the Karlsruhe Research Center. The plant was initially run as KNK I with a thermal core between 1971 and 1974 and then, between 1977 and 1991, with a fast core as the KNK II fast breeder plant. Under the decommissioning concept, the plant is to be decommissioned completely to green field conditions at the end of 2005 in ten steps, i.e. under the corresponding ten decommissioning permits. To this day, nine decommissioning permits have been issued, the first one in 1993 and the most recent one, number nine, in 2001. The decommissioning and demolition activities covered by decommissioning permits 1 to 7 have been completed. Under the 8th Decommissioning Permit, the components of the primary system and the rotating reactor top shield are to be removed by late 2001. Under the 9th Decommissioning Permit, the reactor vessel with its internals, the primary shield, and the biological shield are to be dismantled. The residual sodium volume in the reactor vessel was estimated to amount to approx. 30 l. The maximum Co-60 activation is on the order of 107-108 …
Date: February 27, 2002
Creator: Hillebrand, I. & Benkert, J.
Object Type: Article
System: The UNT Digital Library