65 research outputs found
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RISKIND: An enhanced computer code for National Environmental Policy Act transportation consequence analysis
The RISKIND computer program was developed for the analysis of radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel (SNF) or other radioactive materials. The code is intended to provide scenario-specific analyses when evaluating alternatives for environmental assessment activities, including those for major federal actions involving radioactive material transport as required by the National Environmental Policy Act (NEPA). As such, rigorous procedures have been implemented to enhance the code`s credibility and strenuous efforts have been made to enhance ease of use of the code. To increase the code`s reliability and credibility, a new version of RISKIND was produced under a quality assurance plan that covered code development and testing, and a peer review process was conducted. During development of the new version, the flexibility and ease of use of RISKIND were enhanced through several major changes: (1) a Windows{sup {trademark}} point-and-click interface replaced the old DOS menu system, (2) the remaining model input parameters were added to the interface, (3) databases were updated, (4) the program output was revised, and (5) on-line help has been added. RISKIND has been well received by users and has been established as a key component in radiological transportation risk assessments through its acceptance by the U.S. Department of Energy community in recent environmental impact statements (EISs) and its continued use in the current preparation of several EISs
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RESRAD connection for facilitating MARSSIM analysis : an illustration of applying the OpenLink concept.
The focus of this work is to more tightly integrate tools traditionally used in MARSSIM (Multi-Agency Radiation Survey and Site Investigation Manual) final status survey design. MARSSIM provides guidance on appropriate methodologies for establishing that dose or risk-based standards for a site contaminated with radionuclides have been achieved. RESidual RADioactive (RESRAD) codes are used by the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and other federal agencies to convert dose-based cleanup criteria to site-specific-derived concentration guideline level (DCGL) requirements. By implementing MARSSIM concepts directly within RESRAD, users can now directly generate site-specific DCGL requirements and associated area factors
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Applications of RESRAD family of computer codes to sites contaminated with radioactive residues.
The RESIL4D family of computer codes was developed to provide a scientifically defensible answer to the question ''How clean is clean?'' and to provide useful tools for evaluating human health risk at sites contaminated with radioactive residues. The RESRAD codes include (1) RESRAD for soil contaminated with radionuclides; (2) RESRAD-BUILD for buildings contaminated with radionuclides; (3) RESRAD-CHEM for soil contaminated with hazardous chemicals; (4) RESRAD-BASELINE for baseline risk assessment with measured media concentrations of both radionuclides and chemicals; (5) RESRAD-ECORISK for ecological risk assessment; (6) RESRAD-RECYCLE for recycle and reuse of radiologically contaminated metals and equipment; and (7) RESRAD-OFFSITE for off-site receptor radiological dose assessment. Four of these seven codes (RESRAD, RESRAD-BUILD, RESRAD-RECYCLE, and RESRAD-OFFSITE) also have uncertainty analysis capabilities that allow the user to input distributions of parameters. RESRAD has been widely used in the United States and abroad and approved by many federal and state agencies. Experience has shown that the RESRAD codes are useful tools for evaluating sites contaminated with radioactive residues. The use of RESRAD codes has resulted in significant savings in cleanup cost. Analysis of 19 site-specific uranium guidelines is discussed in the paper
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User's manual for RESRAD version 6.
This manual provides information on the design and application of the RESidual RADioactivity (RESRAD) code. It describes the basic models and parameters used in the RESRAD code to calculate doses and risks from residual radioactive materials and the procedures for applying these models to calculate operational guidelines for soil contamination. RESRAD has undergone many improvements to make it more realistic in terms of the models used in the code and the parameters used as defaults. Version 6 contains a total of 145 radionuclides (92 principal and 53 associated radionuclides), and the cutoff half-life for associated radionuclides has been reduced to 1 month. Other major improvements to the RESRAD code include its ability to run uncertainty analyses, additional options for graphical and text output, a better dose conversion factor editor, updated databases, a better groundwater transport model for long decay chains, an external ground radiation pathway model, an inhalation area factor model, time-integration of dose and risk, and a better graphical user interface. In addition, RESRAD has been benchmarked against other codes in the environmental assessment and site cleanup arena, and RESRAD models have been verified and validated
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Environmental impacts of options for disposal of depleted uranium tetrafluoride (UF{sub 4}).
The U.S. Department of Energy (DOE) evaluated options for managing its depleted uranium hexafluoride (UF{sub 6}) inventory in the Programmatic Environmental Impact Statement for the Long-Term Management and Use of Depleted Uranium Hexafluoride (PEIS) of April 1999. Along with the impacts from other management options, the PEIS discussed the environmental impacts from the disposal of depleted uranium oxide, which could result from the chemical conversion of depleted UF{sub 6}. It has been suggested that the depleted UF{sub 6} could also be converted to uranium tetrafluoride (UF{sub 4}) and disposed of. This report considers the potential environmental impacts from the disposal of DOE's depleted UF{sub 6} inventory after its conversion to UF{sub 4}. The impacts were evaluated for the same three disposal facility options that were considered in the PEIS for uranium oxide: shallow earthen structures, belowground vaults, and mines. They were evaluated for a dry environmental setting representative of the western United States. To facilitate comparisons and future decision making, the depleted UF{sub 4} disposal analyses performed and the results presented in this report are at the same level of detail as that in the PEIS
Verificação do funcionamento de derivações ventrÃculo-peritoneais com válvula mediante emprego de radioisótopos: contribuição técnica pessoal
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Need for multiple approaches in collaborative software development.
The need to share software and reintegrate it into new applications presents a difficult but important challenge. Component-based development as an approach to this problem is receiving much attention in professional journals and academic curricula. However, there are many other approaches to collaborative software development that might be more appropriate. This paper reviews a few of these approaches and discusses criteria for the conditions and contexts in which these alternative approaches might be more appropriate. This paper complements the discussion of context-based development team organizations and processes. Examples from a small development team that interacts with a larger professional community are analyzed
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