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20
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Managing the Nuclear Legacy in the United Kingdom: Strategies and Progress in the Formation of a Liabilities Management Authority
This presentation describes the status of recent initiatives undertaken by the United Kingdom Government to address the long-standing problems confronting it with regards to discharge of public sector civil nuclear liabilities. It describes the enabling steps taken thus far in the creation of a Liabilities Management Unit (LMU) to prepare the ground for this important work, with specific reference to some of the more technically challenging problems which must be resolved in order to make progress towards cleaning up the UK's nuclear legacy facilities and waste materials. Finally, it addresses some of the approaches proposed by the LMU as it seeks to establish a robust, permanent entity to meet the challenges.
Date:
February 25, 2003
Creator:
Edwards, A. & Meyers, B.
Object Type:
Article
System:
The UNT Digital Library
Removal of Dioxin Contamination for Gas Turbine Generator Set Repair
Decontamination projects are typically undertaken in the interest of reducing disposal costs. This goal can be achieved because decontamination concentrates the contaminant into a smaller volume or changes its form so that a lower cost disposal technology becomes available. Less frequently, decontamination adds value back to the fouled structure or contaminated piece of equipment. This removal of dioxins from a gas turbine generator set is one of the latter cases. A multi-million dollar piece of equipment could have been destined for the scrap pile. Instead, an innovative, non-destructive decontamination technology, developed under EPA and DOE demonstration programs has was employed so that the set could repaired and put back into service. The TechXtractchemical decontamination technology reduced surface dioxin / furan concentrations from as high as 24,000 ng / m2 to less than 25 ng / m2 and below detection limits.
Date:
February 25, 2003
Creator:
Fay, W. Scott & Borah, Ronald E.
Object Type:
Article
System:
The UNT Digital Library
Response of a Spent Fuel Transportation Cask to a Tunnel Fire Event
The staff of the Spent Fuel Project Office at the U.S. Nuclear Regulatory Commission undertook the investigation and thermal analysis of the Baltimore tunnel fire event. This event occurred in the Howard Street tunnel, in Baltimore, Maryland, on July 18, 2001. The staff was tasked with assessing the consequences of this event on the transportation of spent nuclear fuel. This paper describes the staff's coordination with the following government and laboratory organizations: the National Transportation Safety Board (NTSB), to determine the details of the train derailment and fire; the National Institute of Standards and Technology (NIST), to quantify the thermal conditions within the tunnel; the Center for Nuclear Waste Regulatory Analysis (CNWRA), to validate the NIST evaluations, and the Pacific Northwest National Laboratory (PNNL), to assist in the thermal analysis. The results of the staff's review and analysis efforts are also discussed. The staff has concluded that had the spent fuel transportation cask analyzed, a design approved under 10 CFR Part 71, been subjected to the Howard Street tunnel fire, no release of radioactive materials would have resulted from this postulated event, and the health and safety of the public would have been maintained.
Date:
February 25, 2003
Creator:
Bajwa, C. S.
Object Type:
Article
System:
The UNT Digital Library
Implications of the Baltimore Rail Tunnel Fire for Full-Scale Testing of Shipping Casks
The U.S. Nuclear Regulatory Commission (NRC) does not currently require full-scale physical testing of shipping casks as part of its certification process. Stakeholders have long urged NRC to require full-scale testing as part of certification. NRC is currently preparing a full-scale casktesting proposal as part of the Package Performance Study (PPS) that grew out of the NRC reexamination of the Modal Study. The State of Nevada and Clark County remain committed to the position that demonstration testing would not be an acceptable substitute for a combination of full-scale testing, scale-model tests, and computer simulation of each new cask design prior to certification. Based on previous analyses of cask testing issues, and on preliminary findings regarding the July 2001 Baltimore rail tunnel fire, the authors recommend that NRC prioritize extra-regulatory thermal testing of a large rail cask and the GA-4 truck cask under the PPS. The specific fire conditions and other aspects of the full-scale extra-regulatory tests recommended for the PPS are yet to be determined. NRC, in consultation with stakeholders, must consider past real-world accidents and computer simulations to establish temperature failure thresholds for cask containment and fuel cladding. The cost of extra-regulatory thermal testing is yet to be determined. …
Date:
February 25, 2003
Creator:
Halstead, R. J. & Dilger, F.
Object Type:
Article
System:
The UNT Digital Library
Radiation Doses to the Public From the Transport of Spent Nuclear Fuel
This paper reviews issues that have been raised concerning radiological risks and safety of the public exposed to shipments of spent nuclear fuel and high-level radioactive waste to a Yucca Mountain repository. It presents and analyzes the contrasting viewpoints of opponents and proponents, presents facts about radiological exposures and risks, and provides perspective from which to observe the degree of risk that would devolve from the shipments. The paper concludes that the risks to the public's health and safety from being exposed to radiation from the shipments will not be discernable.
Date:
February 25, 2003
Creator:
Best, R. E.; Maheras, S. J.; Ross, S. S. & Weiner, R.
Object Type:
Article
System:
The UNT Digital Library
The Use of DOE Technologies at The World Trade Center Incident: Lessons Learned
In response to the attack of the World Trade Center (WTC) on September 11, 2001, the International Union of Operating Engineers (IUOE) National Hazmat Program (OENHP) assembled and deployed a HAZMAT Emergency Management Team (Team) to the disaster site (Site). The response team consisted of a Certified Industrial Hygienist and a rotating team of industrial hygienists, safety professionals, and certified HAZMAT instructors. Through research funded by the Department of Energy (DOE) Office of Environmental Management (EM) and managed by the National Energy Technology Laboratory (NETL), the IUOE conducted human factors assessments on baseline and innovative technologies during real-world conditions and served as an advocate at the WTC disaster site to identify opportunities for the use and evaluation of DOE technologies. From this work, it is clear that opportunities exist for more DOE technologies to be made readily available for use in future emergencies.
Date:
February 25, 2003
Creator:
McCabe, B.; Kovach, J.; Carpenter, C. & Blair, D.
Object Type:
Article
System:
The UNT Digital Library
Implementation of Revision 19 of the TRUPACT-II Safety Analysis Report at Rocky Flats Environmental Technology Site
The U.S. Nuclear Regulatory Commission on July 27, 2001 approved Revision 19 of the TRUPACT-II Safety Analysis Report (SAR) and the associated TRUPACT-II Authorized Methods for Payload Control (TRAMPAC). Key initiatives in Revision 19 included matrix depletion, unlimited mixing of shipping categories, a flammability assessment methodology, and an alternative methodology for the determination of flammable gas generation rates. All U.S. Department of Energy (DOE) sites shipping transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) were required to implement Revision 19 methodology into their characterization and waste transportation programs by May 20, 2002. An implementation process was demonstrated by the Rocky Flats Environmental Technology Site (RFETS) in Golden, Colorado. The three-part process used by RFETS included revision of the site-specific TRAMPAC, an evaluation of the contact-handled TRU waste inventory against the regulations in Revision 19, and design and development of software to facilitate future inventory analyses.
Date:
February 25, 2003
Creator:
D'Amico, E.; O'Leary, J.; Bell, S.; Djordjevic, S.; Givens, C,; Shokes, T. et al.
Object Type:
Article
System:
The UNT Digital Library
The Challenge Now: Completion of the Legacy TRU Waste Mission 20 Years Early
The Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) opened on March 26, 1999, becoming the nation's first deep geologic repository for the permanent disposal of defense generated transuranic (TRU) waste. This waste is currently retrievably stored at 27 sites across the country. Since its opening, approximately 10,000 m3 of TRU waste have been safely characterized, transported, and disposed in the WIPP. The DOE has achieved and surpassed the original goal of sending 17 waste shipments per week to WIPP. The National TRU Program (NTP) has implemented significant operational efficiencies, regulatory changes, and management initiatives, but the program cannot rest on its past achievements. The initial program schedule shows completion of TRU waste disposal in 2034 at an estimated life-cycle cost of $16 billion. The Carlsbad Field Office (CBFO) and the 27 TRU waste generator sites have developed a comprehensive plan that will allow completion of the legacy TRU waste mission 20 years ahead of the initial schedule.
Date:
February 25, 2003
Creator:
Triay, I. & Wu, C.
Object Type:
Article
System:
The UNT Digital Library
Issues at Stake When Considering Long Term Storage of HLW a Comprehensive Approach to Designing the Facility
CEA has been conducting a comprehensive R&D program to identify and study key HLW storage design criteria to possibly meet the lifetime goal of a century and beyond. A novel approach is being used since such installations must be understood as a global system comprised of various materials and hardware components, canisters, concrete and steel structures and specific procedures covering engineering steps from construction to operation including monitoring, care and maintenance as well as licensing. The challenge set by such a lifetime design goal made the R&D people focus on issues at stake and relevant to long term HLW storage in particular heat management, the effect of time on materials and the sustainability of care and maintenance. This opened up the R&D field from fundamental research areas to more conventional and technical aspects. Two major guiding principles have been devised as key design goals for the storage concepts under consideration. One is the paramount function of retrievability, which must allow the safe retrieval of any HLW package from the facility at any given time. Next is the passive containment philosophy requiring that a dual-barrier system be considered. In the case of spent fuel, CEA's early assessment of the long-term behavior …
Date:
February 25, 2003
Creator:
Marvy, A. & Ochem, D.
Object Type:
Article
System:
The UNT Digital Library
The Challenges of Creating a Real-Time Data Management System for TRU-Mixed Waste at the Advanced Mixed Waste Treatment Plant
This paper discusses the challenges associated with creating a data management system for waste tracking at the Advanced Mixed Waste Treatment Plant (AMWTP) at the Idaho National Engineering Lab (INEEL). The waste tracking system combines data from plant automation systems and decision points. The primary purpose of the system is to provide information to enable the plant operators and engineers to assess the risks associated with each container and determine the best method of treating it. It is also used to track the transuranic (TRU) waste containers as they move throughout the various processes at the plant. And finally, the goal of the system is to support paperless shipments of the waste to the Waste Isolation Pilot Plant (WIPP). This paper describes the approach, methodologies, the underlying design of the database, and the challenges of creating the Data Management System (DMS) prior to completion of design and construction of a major plant. The system was built utilizing an Oracle database platform, and Oracle Forms 6i in client-server mode. The underlying data architecture is container-centric, with separate tables and objects for each type of analysis used to characterize the waste, including real-time radiography (RTR), non-destructive assay (NDA), head-space gas sampling and …
Date:
February 25, 2003
Creator:
Paff, S. W & Doody, S.
Object Type:
Article
System:
The UNT Digital Library
Radioactive Waste Management in Hungary at the Turn of the Millennium 1
The paper deals with the Hungarian radioactive waste management practice from the beginning up to now. It gives a historical overview which is extended with the detailed description of activity of the present temporary waste disposal facility in Puespoekszilagy. In addition the plan for improving of the facility is also discussed.
Date:
February 25, 2003
Creator:
Pellet, S.; Temesi, A. & Fritz, A.
Object Type:
Article
System:
The UNT Digital Library
Comparison of LiFePO4 from different sources
The lithium iron phosphate chemistry is plagued by the poor conductivity and slow lithium diffusion in the solid phase. In order to alleviate these problems, various research groups have adopted different strategies including decreasing the particle sizes, increasing the carbon content, and adding dopants. In this study we obtained LiFePO4 electrodes from six different sources and used a combined model-experimental approach to compare the performance. Samples ranged from one with no carbon coating to one with 15 percent coating. In addition, particle sizes varied by as much as a order of magnitude between samples. The study detailed in this manuscript allows us to provide insight into the relative importance of the conductivity of the samples compared to the particle size, the impact of dopant on performance and ideas for making materials in order to maximize the power capability of this chemistry.
Date:
November 25, 2003
Creator:
Striebel, Kathryn; Shim, Joongpyo; Srinivasan, Venkat & Newman, John
Object Type:
Article
System:
The UNT Digital Library
Thorough Chemical Decontamination with the MEDOC Process : Batch Treatment of Dismantled Pieces or Loop Treatment of Large Components Such as the BR3 Steam Generator and Pressurizer
The dismantling of the BR3-PWR reactor leads to the production of large masses of contaminated metallic pieces, including structural materials, primary pipings, tanks and heat exchangers. One of our main objectives is to demonstrate that we can minimize the volume of radioactive waste in an economical way, by the use of alternative waste routes, such as the clearance of materials after thorough decontamination. The SCKoCEN uses its own developed chemical decontamination process, so-called MEDOC (Metal Decontamination by Oxidation with Cerium), based on the use of cerium IV as strong oxidant in sulphuric acid with continuous regeneration using ozone. An industrial installation has been designed and constructed in close collaboration with Framatome-ANP (France). This installation started operation in September 1999 for the treatment of the metallic pieces arising from the dismantling of the BR3 reactor. Since then, more than 25 tons of contaminated material including primary pipes have been treated batchwise with success. 75 % of material could be directly cleared after treatment (Activity lower than 0.1 Bq/g for 60Co) and the other 25% free released after melting activity. The SCKoCEN performed in April 2002 the closed loop decontamination of the BR3 Steam Generator by connection of the MEDOC plant after …
Date:
February 25, 2003
Creator:
Ponnet, M.; Klein, M.; Massaut, V.; Davain, H. & Aleton, G.
Object Type:
Article
System:
The UNT Digital Library
Waste Generated from LMR-AMTEC Reactor Concept
The candidate Liquid Metal Reactor-Alkali Metal Thermal -to- Electric Converter (LMR-AMTEC) is considered to be the first reactor that would use pure liquid potassium as a secondary coolant, in which potassium vapor aids in the conversion of thermal energy to electric energy. As with all energy production, the thermal generation of electricity produces wastes. These wastes must be managed in ways which safeguard human health and minimize their impact on the environment. Nuclear power is the only energy industry, which takes full responsibility for all its wastes. Based on the candidate design of the LMR-AMTEC components and the coolant types, different wastes will be generated from LMR. These wastes must be classified and characterized according to the U.S. Code of Federal Regulation, CFR. This paper defines the waste generation and waste characterization from LMR-AMTEC and reviews the applicable U.S. regulations that govern waste transportation, treatment, storage and final disposition. The wastes generated from LMR-AMTEC are characterized as: (1) mixed waste which is generated from liquid sodium contaminated by fission products and activated corrosion products; (2) hazardous waste which is generated from liquid potassium contaminated by corrosion products; (3) spent nuclear fuel; and (4) low-level radioactive waste which is generated from …
Date:
February 25, 2003
Creator:
Hasan, Ahmed; Mohamed, Yasser, T. & Mohammaden, Tarek, F.
Object Type:
Article
System:
The UNT Digital Library
Characterization of high-power lithium-ion cells-performance and diagnostic analysis
Lithium-ion cells, with graphite anodes and LiNi0.8Co0.15Al0.05O2 cathodes, were cycled for up to 1000 cycles over different ranges of SOC and temperatures. The decline in cell performance increases with the span of SOC and temperature during cycling. Capacity fade was caused by a combination of the loss of cycleable Li and degradation of the cathode. The room temperature anodes showed SEI compositions and degrees of graphite disorder that correlated with the extent of the Li consumption, which was linear in cell test time. TEM of the cathodes showed evidence of crystalline defects, though no major new phases were identified, consistent with XRD. No evidence of polymeric deposits on the cathode particles (FTIR) was detected although both Raman and TEM showed evidence of P-containing deposits from electrolyte salt degradation. Raman microscopy showed differences in relative carbon contents of the cycled cathodes, which is blamed for part of the cathode degradation.
Date:
November 25, 2003
Creator:
Striebel, K. A.; Shim, J.; Kostecki, R.; Richardson, T. J.; Ross, P. N.; Song, X. et al.
Object Type:
Article
System:
The UNT Digital Library
Proteomics: Technology and Applications
This meeting took place at the Keystone, Colorado resort from March 25-30, 2003. It was attended by 206 participants, of which 35 were students; 39% of attendees submitted abstracts. The meeting had 30% returning attendees and 70% new attendees. The group of speakers was composed of internationally recruited junior and senior experts in their respective fields. The group included representatives from academia and the private sector, highlights the convergence of proteomics efforts in the two sectors. The completion of the genome sequences of a large number of prokaryotic and eukaryotic species has catalyzed new research approaches to study the structure, function and control of biological processes. They are characterized by the systematic and in many cases quantitative analysis of all the molecules of a particular type expressed by a cell or tissue. The systematic analysis of proteins has been terms ''proteomics''. In an initial phase, most of the proteomics efforts were focused on large-scale protein identification. More recently, the objectives and technologies of proteomics have been diversified and expanded. Current proteomics research attempts to systematically and, where applicable, quantitatively determine the many properties of proteins and their biological function, including: protein abundance, state of modification, specific activity, interaction with other …
Date:
March 25, 2003
Creator:
Aebersold, Ruedi
Object Type:
Report
System:
The UNT Digital Library
Fibrous Monolith Wear Resistant Components for the Mining Industry Semi-Annual Report: Number 4
During the reporting period, work continued on development of formulations using the materials down-selected from the initially identified contenders for the fibrous monolith wear resistant components. In the previous reporting period, a two-stage binder removal process was developed that resulted in prototype parts free of voids and other internal defects. During the current reporting period, work was performed to characterize the two-stage binder removal process for WC-Co based FM material systems. Use of this process has resulted in the fabrication of defect free sintered WC-Co FM bodies, with minimal free carbon porosity and densities approaching 100% theoretical. With the elimination of free carbon porosity and other binder removal process related defects, development work focused on optimizing the densification and eliminating defects observed in WC-Co based FM consolidated by pressureless sintering. Shrinkage of the monolithic core and shell materials used in the WC-Co based FM system was measured, and differences in material shrinkage were identified as a potential cause of cell boundary cracking observed in sintered parts. Re-formulation of material blends for this system was begun, with the goal of eliminating mechanical stresses during sintering by matching the volumetric shrinkage of the core and shell materials. Thirty-three 7/8 inch drill bit …
Date:
March 25, 2003
Creator:
Rigali, Mark J. & Fulcher, Mike L.
Object Type:
Report
System:
The UNT Digital Library
The Universal Canister Strategy in Spent Fuel Reprocessing: UC-C a Real Industrial Improvement
In commercial nuclear activities, spent fuel back end management is a key issue for nuclear countries as spent fuel represent most of national civil nuclear waste legacy. Ensuring public safety and protection of the environment, now and in the future has been and still remains a major commitment, it is still the subject of thorough development efforts and active public debates. Considerable benefits can be obtained from the Universal Canister strategy as implemented in France in spent fuel treatment and waste conditioning based on reprocessing. COGEMA developed sophisticated waste conditioning processes to simplify High Level and Long Lived Intermediate Level Waste storage and final disposal. Main benefits are: waste stabilization by immobilization and encapsulation; ultimate waste toxicity reduction; drastic ultimate waste volume reduction; and ultimate waste packages standardization.
Date:
February 25, 2003
Creator:
Thomasson, J.; Barithel, S.; Cocaud, A.; Derycke, P. & Pierre, P.
Object Type:
Article
System:
The UNT Digital Library
The EPRI DFDX Chemical Decontamination Process
Decommissioning of retired nuclear plants and components demands the proper management of the process, both for economic reasons and for retaining public confidence in the continued use of nuclear power for electricity generation. The cost and ease of management of radioactively contaminated components can be greatly assisted by the application of decontamination technology. EPRI initiated a program of research and development work in collaboration with Bradtec, which has led to the ''EPRI DFD'' (Decontamination for Decommissioning) Process. The Process has been patented and licensed to six companies worldwide. The purpose of this process is to achieve efficient removal of radioactivity with minimum waste from retired nuclear components and plant systems. The process uses dilute fluoroboric acid with controlled oxidation potential. By removing all the outer scale and a thin layer of base metal from the surfaces, contamination can in many cases be reduced below the levels required to allow clearance (free-release) or recycle to form new components for the nuclear industry. This reduces the need for on-site storage or burial of large amounts of contaminated material at low level radioactive disposal facilities. An additional benefit is that residual radiation fields can be reduced by a large factor, which reduces the …
Date:
February 25, 2003
Creator:
Bushart, S.; Wood, C. J.; Bradbury, D. & Elder, G.
Object Type:
Article
System:
The UNT Digital Library
Fracture toughness and crack growth rates of irradiated austenitic stainless steels.
Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10{sup 21} n/cm{sup 2} (E > 1 MeV) ({approx}3.0 dpa) at {approx}288 C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling water reactor (BWR) environments, and fracture toughness tests were conducted in air. Neutron irradiation at 288 C decreases the fracture toughness of the steels; the data from commercial heats fall within the scatter band for the data obtained at higher temperatures. In addition, the results indicate significant enhancement of CGRs of the irradiated steels in normal water chemistry BWR environment; the CGRs for irradiated steels are a factor of {approx}5 higher than the disposition curve proposed for sensitized austenitic SSs. The rates decreased by more than an order of magnitude in low-dissolved-oxygen BWR environment.
Date:
June 25, 2003
Creator:
Chopra, O. K.; Gruber, E. E. & Shack, W. J.
Object Type:
Report
System:
The UNT Digital Library
Waste Generator Services--From Chaos and Confusion to Order and Compliance
Waste management practices at the Department of Energy's (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) have dramatically improved during the past four years. Past methods had resulted in a backlog of inadequately characterized waste stored at numerous locations scattered throughout the INEEL site, lack of knowledge of treatment capabilities, and absence of waste accountability. Escalating Resource Conservation and Recovery Act (RCRA) violations and associated fines averaged $800,000 annually. Since the implementation of Waste Generator Services (WGS), a centralized waste management organization, waste backlog has been significantly reduced and contracts have been established with numerous commercial facilities for treatment and disposal of hazardous waste, low-level waste, and mixed low-level waste. Waste traceability and accountability have improved, and the number of violations has significantly decreased. WGS has also made a significant contribution in fin e reduction, which averaged approximately $134,000 between 1998 through 2000, with Fiscal Year 2001 fines negotiated at just $12,000a. Temporary Accumulation Areas (TAAs) used for storage of waste for periods of less than 90 days, have been consolidated from 42 to 12. This consolidation has resulted in fewer areas that are more easily managed, each tracked and controlled by an assigned custodian. Additionally, the backlog of stored …
Date:
February 25, 2003
Creator:
Kaptein, Michelle; Orme, Jason & Rohe, Rhonda
Object Type:
Article
System:
The UNT Digital Library
U.S. DOE Approach to Address U.S. NRC Key Technical Issues for a License Application
Interactions between the U.S. Department of Energy (DOE) staff and the U.S. Nuclear Regulatory Commission (NRC) staff prior to submittal of a license application (LA) for NRC review are focused on resolution of issues relevant to licensing a geologic repository at the Yucca Mountain site. These interactions take place in meetings that are open to the public, the State of Nevada, affected units of local government, and other interested parties. Consistent with a 1992 agreement between the DOE and NRC, resolution of an issue at the staff level can be achieved during the pre-licensing period when the NRC staff has no further questions or comments regarding how the DOE is addressing that issue. In no case does such resolution at the NRC staff level preclude an issue being raised during the licensing proceedings by the NRC or another party to the proceedings. Beginning in 1996, interactions between the DOE and NRC began to focus significant attention on the nine topical areas, called Key Technical Issues (KTIs), that the NRC staff considers to be important in evaluating the post-closure performance of a Yucca Mountain repository. DOENRC meetings to discuss each KTI and achieve technical agreement on the information needed to resolve …
Date:
February 25, 2003
Creator:
Ziegler, J. D.; Gunter, T. C.; Gamble, R. P. & Bradbury, R. B.
Object Type:
Article
System:
The UNT Digital Library
The Swedish Program has Entered the Site Selection Phase
Facilities for intermediate storage of spent fuel and HLW and for final disposal of ILW and LLW together with a system for sea transportation have been in operation in Sweden for more then 15 years. To complete the ''back end system'' the remaining parts are to build facilities for encapsulation and final storage of spent fuel and HLW. The Swedish reference method for final disposal of spent fuel, KBS-3, is to encapsulate the fuel elements in copper canisters and dispose them in a deep geological repository. The Swedish program up to 2001 was focused on the establishment of general acceptance of the reference method for final storage and SKB's selection of candidate sites for a deep geological repository. In the end of year 2000 SKB presented a report as a base for a Government decision about the siting process. This report gave the background for the selection of three candidate sites. It also presented the program for geological surveys of the candidate sites as well as the background for the choice of the method for final disposal of spent nuclear fuel and HLW. In the end of 2001 the Swedish government endorsed the plan for the site selection phase and …
Date:
February 25, 2003
Creator:
Nygards, P.; Hedman, T.; Eng, T. & Olsson, O.
Object Type:
Article
System:
The UNT Digital Library
Post 9-11 Security Issues for Non-Power Reactor Facilities
This paper addresses the legal and practical issues arising out of the design and implementation of a security-enhancement program for non power reactor nuclear facilities. The security enhancements discussed are derived from the commercial nuclear power industry's approach to security. The nuclear power industry's long and successful experience with protecting highly sensitive assets provides a wealth of information and lessons that should be examined by other industries contemplating security improvements, including, but not limited to facilities using or disposing of nuclear materials. This paper describes the nuclear industry's approach to security, the advantages and disadvantages of its constituent elements, and the legal issues that facilities will need to address when adopting some or all of these elements in the absence of statutory or regulatory requirements to do so.
Date:
February 25, 2003
Creator:
Zaffuts, P. J.
Object Type:
Article
System:
The UNT Digital Library