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At least 1,729 records · Page 96

Options of system integrated environment modelling in the predicated dynamic cyberspace

In this article there are briefly mentioned some selected options of contemporary conception of cybernetic system models in the corresponding and possible integratable environment with modern system dynamics thinking and all this in the cyberspace of possible projecting of predicted system characteristics. The key to new capabilities of system integration modelling in the considered cyberspace is mainly the ability to improve the environment and the system integration options, all this with the aim of modern control in the hierarchically arranged dynamic cyberspace, e.g. in the currently desired electronic business with information. The aim of this article is to assess generally the trends in the use of modern modelling methods considering the cybernetics applications verified in practice, modern concept of project management and also the potential integration of artificial intelligence in the new projecting and project management of integratable and intelligent models, e.g. with the optimal structures and adaptable behaviour.The article results from the solution of a specific research partial task at the faculty; especially the moments proving that the new economics will be based more and more on information, knowledge system defined cyberspace of modern management, are stressed in the text.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗

The Glory Program: Global Science from a Unique Spacecraft Integration

The Glory program is an Earth and Solar science mission designed to broaden science community knowledge of the environment. The causes and effects of global warming have become a concern in recent years and Glory aims to contribute to the knowledge base of the science community. Glory is designed for two functions: one is solar viewing to monitor the total solar irradiance and the other is observing the Earth s atmosphere for aerosol composition. The former is done with an active cavity radiometer, while the latter is accomplished with an aerosol polarimeter sensor to discern atmospheric particles. The Glory program is managed by NASA Goddard Space Flight Center (GSFC) with Orbital Sciences in Dulles, VA as the prime contractor for the spacecraft bus, mission operations, and ground system. This paper will describe some of the more unique features of the Glory program including the integration and testing of the satellite and instruments as well as the science data processing. The spacecraft integration and test approach requires extensive analysis and additional planning to ensure existing components are successfully functioning with the new Glory components. The science mission data analysis requires development of mission unique processing systems and algorithms. Science data analysis and distribution will utilize our national assets at the Goddard Institute for Space Studies (GISS) and the University of Colorado's Laboratory for Atmospheric and Space Physics (LASP). The Satellite was originally designed and built for the Vegetation Canopy Lidar (VCL) mission, which was terminated in the middle of integration and testing due to payload development issues. The bus was then placed in secure storage in 2001 and removed from an environmentally controlled container in late 2003 to be refurbished to meet the Glory program requirements. Functional testing of all the components was done as a system at the start of the program, very different from a traditional program. The plan for Glory is to minimize any changes to the spacecraft in order to meet the Glory requirements. This means that the instrument designs must adhere to the existing interfaces and capabilities as much as possible. Given Glory's unique history and the potential science return, the program is one of significant value to both the science community and the world. The findings Glory promises will improve our understanding of the drivers for global climate change for a minimal investment. The program hopes to show that reuse of existing government assets can result in a lower cost, and fully successful mission.

Bajpayee Jaya↗

The Journey to Vulnerability Management?

Abstract Text Idaho National Laboratory’s Information Management (IM) is transforming how they manage IT vulnerabilities. The IM team realized the increasing risks to the Lab and the difficulty of ‘keeping tabs’ on multiple organizations and multiple process for Vulnerability Management (VM). They chose to stand up an IT Operations and Vulnerability Management group to help centralize VM across IM organizations. Come listen and participate as we describe the on-going journey to facilitating a centralized vulnerability management operation. A mature VM program should provide a manageable life cycle for vulnerabilities and variances. In addition, the program must provide visibility to management and stakeholders for continuous monitoring and reporting of vulnerability discovery and remediation across Applications, Databases, Workstations, Servers, Infrastructure Equipment, and remediation of Variances.

97 MATHEMATICS AND COMPUTING↗

The High Capacity Type B Waste Transport Cask to Serve Dismantling Project - 18344

The United States have already announced around 20 reactor shutdown and many more in the next 10 year. Financial constraints on plant operators and the low cost of fossil energy contribute to accelerate the shutdown of additional reactors. The industry has been gaining experience with reactor dismantling and is continuously trying to improve the cost efficiency of the upcoming projects. To do so, larger and more capacitive transport casks are needed to transport increasing volume of Low Level Waste (LLW) at a more attractive cost. Waste disposal is also a major cost element in a dismantling project. Consequently, the capacity to segment, package and transport the waste in the most optimized configuration will result in significant cost savings. While for LLW, the constraints for package requirements are limited, activated waste resulting mainly from reactor vessel and vessel internals segmentation require additional shielding to meet disposal and transportation regulations. The key element to succeed is the availability on the market of a licensed type B transport package with a larger payload that allows at the same time an optimization of the waste segmentation. AREVA TN has designed and licensed versatile high capacity type B casks for the transport of spent fuel canisters as part of the NUHOMS{sup R} system that can also be used to transport radioactive waste. While it will take a few more years to transport spent fuel to a consolidated interim storage facility and even more to a repository, the type B casks can be used to transport activated LLW from dismantled reactors to disposal sites. A first of a kind project will be performed with AREVA's partner NorthStar at Vermont Yankee Nuclear Power Plant. AREVA's team will perform the reactor segmentation and package the material into an AREVA's large capacity type B cask. This unmatched cask capacity is expected to significantly decrease the LLW disposal costs, as well as the onsite operations costs, while optimizing the schedule. The package will be transported by rail to waste disposal facilities. This paper will present the main characteristics of the package, provide an update of the overall schedule, and explain the innovations that contribute to simpler and more cost effective transport and operation. Finally, it will emphasize the benefits of using larger type B casks for immediate and future transportation needs. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Safe and Secure Management of Disused Radioactive Sealed Sources in Egypt - 19063

Radioactive sources offer many benefits in medicine, industry and education but the lack of appropriate long-term management when they eventually become disused has led to accidents, in some cases with serious consequences, and increased their vulnerability for use in a malicious act. This lack is evident in the absence of clearly defined policy and strategy, responsibilities and resources to meet those responsibilities for safe, secure and sustainable management of disused sources. The strengthening of national legislative and regulatory infrastructures globally has led to major improvements in the protection and control of radioactive sources. Nevertheless, in many countries, radioactive sources were in use before such infrastructures had been developed or adequately strengthened and were therefore not under regulatory control. The paper presents some aspects from Egyptian experience related to safe and secure measures for management of Cs-137, Ra-226 and Co-60 sealed sources. Data relating to the disused radioactive sealed sources, DSRS inventory as well as the arrangements made in order to prepare for conditioning of sources is presented. The efforts made by technical staff and radiation protection team for all arrangements and details such as conditioning set-up, working area, leakage test, certified stainless capsules, radiation protection measures and sources characterization in addition to all security measures for stored DSRS are also presented. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Error Analysis of CM Data Products Input Distributions

This goal of this project is to address the current inability to assess the overall error and uncertainty of data products developed and distributed by DOE’s Consequence Management (CM) Program.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Integrating regulatory, programmatic and technical needs for modeling tools to support decision-making - 15219

The U.S. Department of Energy (US DOE) Office of Environmental Management (EM), Office of Soil and Groundwater Remediation, is supporting development of the Advanced Simulation Capability for Environmental Management (ASCEM). ASCEM provides a modeling work-flow to support decision-making for site restoration, tank closure and waste management activities. Potential users involved in regulatory applications (e.g., performance and risk assessments and other activities supporting regulatory decisions) are a key target group for the tool-set. Decision-making in these applications often requires consideration of multiple perspectives, including: regulators and the public, oversight and project management personnel, as well as practitioners involved in conducting the calculations, each with different interests. From its inception, a key objective of the ASCEM project has been to actively seek input from these different user perspectives to help guide development. ASCEM formed a User Steering Committee (USC) with membership representing interests from management/staff at DOE Site Contractors, DOE-HQ and Field offices and Regulators (State and Federal). The project also provides opportunities for input from the broader user community through participation in meetings of the Performance and Risk Assessment (P and RA) Community of Practice (CoP), routine briefings and participation in meetings of the Low-Level Waste Disposal Facility Federal Review Group, and direct interactions with users involved in regulatory applications. Interactions with users involved in regulatory applications have influenced the requirements for the tool-sets and are reflected in capabilities that have been and are being implemented. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Authorization to proceed with production engineering for the waste treatment and immobilization plant's high-level waste facility - 15595

The U.S. Department of Energy restricted certain engineering, procurement, and construction work on the Waste Treatment and Immobilization Plant's (WTP) Pretreatment Facility, and to a lesser degree the High-Level Waste (HLW) Facility in 2012 and early 2013 because of the impact of unresolved technical issues on the facility design, and a misalignment between the facility design and nuclear safety basis. The U.S. Department of Energy, Office of River Protection (ORP) needed a way to minimize project management risk, while continuing limited critical path construction work for the HLW Facility and resolving the technical and safety basis issues. ORP developed a process to systematically address and resolve the technical, management, and quality issues that led DOE to restrict HLW Facility production activities in 2012 and 2013. This process provided for a phased resumption of HLW engineering, procurement, and construction activities on an incremental basis and a final decision for release to full production. In August 2014, ORP provided authorization for the WTP contractor to resume all engineering work necessary to finalize the HLW Facility design. The decision to proceed with production engineering in the HLW Facility, representing the first of two decision points, was based on significant progress in resolving HLW technical issues and improving work processes to align the HLW design and safety basis. Full release for HLW equipment procurements and construction is forthcoming based on conditions that must be fully satisfied and demonstrated during a transition period expected to continue for the next few years. (authors)

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Upgrading the JET Remote Handling System - 18356

The Joint European Torus (JET) has employed advanced remote-maintenance techniques for over three decades to avoid exposing humans to a potentially hazardous environment and to develop techniques for future power-generating fusion reactors where environments will be too hazardous for any manned maintenance. As a unique application of robotics, virtual reality and operations management systems, JET's remote handling unit, now a part of RACE, has driven the state-of-the-art with each upgrade programme in its history. This conference paper presents the current capabilities of the JET remote handling system, and the future capabilities being delivered by its latest upgrade programme, which makes use of cutting edge advances. RACE (Remote Applications in Challenging Environments) aims to shape the technologies being developed for JET in such a way that they will have wider applications, such as in nuclear decommissioning. (authors)

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Development of an Alternative Approach to Demonstrating Environmental Performance in the UK - 19354

European basic safety standards require that exposure of humans to the potentially harmful effects of ionising radiation are optimised so that they are as low as reasonably achievable, taking account of economic and societal factors. In the United Kingdom the responsibility for ensuring that exposures to humans are optimised is split between two regulatory functions. The Office of Nuclear Regulation regulates exposures to workers in all scenarios and to members of the public in the event of an accident. Environmental regulators in each of the four nations comprising the United Kingdom regulate exposures to members of the public from normal operations. Since the early 1990's, all permissions granted to nuclear sites in the UK for the discharge/disposal of radioactive waste to the environment have contained conditions requiring holders to demonstrate that they minimise the generation of radioactive waste, apply appropriate abatement and discharge/dispose of it in a way that minimises impacts on members of the public and the environment. For many years, the industry standard for providing this demonstration, which was heavily influenced by regulatory expectations and feedback, was to undertake one or a series of multi-attribute decision assessments (MADA). Wood's team of environmental specialists has been involved in undertaking such MADA studies for many years. Since the mid-2000's, our team has become increasingly aware of some of the limitations of undertaking MADA to demonstrate environmental performance for large scale new nuclear build projects and, in particular, the next generation of new nuclear power stations that are being planned and implemented in the UK. We have collaborated with the vendors of reactor technologies, the prospective/owner operators of new nuclear power stations and the developers of new facilities on existing sites to develop an alternative approach to demonstrating environmental performance. Our alternative approach comprises three main pillars which are summarised as: - Evolution - benefit from progressive improvements, operational experience and recent permitting activities. Our alternative approach uses the claim, argument, evidence approach which is commonly used for nuclear safety cases and which allows us to 'tell the story' of how environmental performance has been achieved. We have successfully deployed this approach for all new nuclear power stations proposed in the UK. - Integration - ensure that optimisation is integrated into the project programme and forms part of the 'big picture'. Our alternative approach allows environmental performance to be managed better throughout the life cycle of the project and ensures that our outputs are 'living' documents and do not 'sit on the shelf'. We have successfully demonstrated how this can be applied during rationalisation of major schemes and significant design changes on nuclear new build projects. - Opportunity - identify the best time to deliver elements of the programme. Our alternative approach aims to minimise the overall time, trouble and costs associated with demonstrating environmental performance by ensuring that decisions are made at the time when they offer greatest benefit and by minimising unnecessary rework. Our advice has helped to reduce the project costs and minimise delays associated with regulatory queries and interventions. This paper describes the journey that we have taken with our clients in developing our alternative approach to demonstrating environmental performance. We explain the UK regulatory context and explore the need for change. We present a number of case studies related to new nuclear power stations and other new facilities on existing nuclear sites that demonstrate the successful application of our alternative approach. We provide examples of how we have successfully implemented the outputs of our alternative approach into project and corporate management arrangements. Finally, we examine feedback from clients, regulators and other interested parties to propose future refinements. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Reliability and Integrity Management Scoping Study

The U.S. Nuclear Regulatory Commission (NRC) is developing the regulatory framework and technical expertise to support regulatory review of advanced non-light water reactor (ANLWR) designs. The NRC staff expects most of these designs to use the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) Section XI, Division 2 “Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants” for developing and implementing pre-service inspection (PSI) and in-service inspection (ISI) programs. The NRC recently endorsed ASME BPVC Section XI, Division 2 (BPV XI-2) in Regulatory Guide (RG) 1.246. This new ASME code is yet to be used in any applications submitted for NRC review. This report provides an overview of the current state of knowledge and practices within the industry for the use of BPV XI-2 for the development and implementation of a PSI and ISI program for non-light water reactors.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

French Geological Disposal Project: From Siting to Permitting - 19018

The future 'Cigeo' geological repository will be located in eastern France, at the border between the Meuse and Haute-Marne. Research has been carried out in this area since the 1990's, leading to the identification of a zone within the Paris basin whose geological characteristics make it suitable for the deep geological disposal of high- and intermediate-level long-lived radioactive waste, as well as a smaller zone of approximately 250 km{sup 2} (proposed in 2005) within which the characteristics of the host layer are very similar to those observed in the Underground Research Laboratory (URL). In 2010, based on additional surveys, a zone of approximately 30 km{sup 2} called ZIRA, in which the industrial underground facility would be constructed was defined. The repository structures within the ZIRA will be located at a depth of 525 metres. Half the surface area of the ZIRA is located in a wooded area, the other half being situated in grassland or farmland. All the subsequent design studies (preliminary and detailed) of Cigeo as well as the preparation of the licensing files (to be submitted in 2020) were conducted on the basis on this precise siting. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Solar Decathlon 2017: Final Report and Lessons Learned

Energetics Incorporated, with its project partners (collectively known as Team Energetics), has prepared the Solar Decathlon 2017 Final Report and Lessons Learned for the U.S. Department of Energy (DOE) to summarize and reflect on the administration of the planning, implementation, and close-out of Solar Decathlon 2017. This final report introduces the Solar Decathlon 2017 Program Administrator, Core Advisory Committee, event sponsors and donors, and regional stakeholders that were integral to the success of Solar Decathlon 2017. The substantial balance of this report presents evaluative metrics and lessons learned about the primary aspects of administering Solar Decathlon 2017, including Project Management, Competition and Site Management, Stakeholder Engagement, Communications, Sponsor Management, Education Programming, and Volunteer Coordination. Several appendices compliment the discussion.

14 SOLAR ENERGY↗

Nevada National Security Site Environmental Report 2018

This report presents the National Nuclear Security Administration Nevada Field Office environmental protection and monitoring programs data and the compliance status for calendar year 2018 at the Nevada National Security Site and at its two support facilities, the North Las Vegas Facility and the Remote Sensing Laboratory-Nellis. This report also addresses environmental restoration projects conducted by the Environmental Management Nevada Program Office at the Tonopah Test Range.

54 ENVIRONMENTAL SCIENCES↗

Nevada National Security Site Environmental Report 2019

This report presents the National Nuclear Security Administration Nevada Field Office environmental protection and monitoring programs data and the compliance status for calendar year 2019 at the Nevada National Security Site and at its two support facilities, the North Las Vegas Facility and the Remote Sensing Laboratory-Nellis. This report also addresses environmental restoration projects conducted by the Environmental Management Nevada Program Office at the Tonopah Test Range.

54 ENVIRONMENTAL SCIENCES↗

Nevada National Security Site 2012 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

This report is a compilation of the groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). The data have been collected since 1993 and include calendar year 2012 results. During 2012, groundwater samples were collected and static water levels were measured at the three pilot wells surrounding the Area 5 RWMS. Groundwater samples were collected at UE5PW-1, UE5PW-2, and UE5PW-3 on March 21, August 7, August 21, and September 11, 2012, and static water levels were measured at each of the three pilot wells on March 19, June 6, August 2, and October 15, 2012. Groundwater samples were analyzed for the following indicators of contamination: pH, specific conductance, total organic carbon, total organic halides, and tritium. Indicators of general water chemistry (cations and anions) were also measured. Final results from samples collected in 2012 were within the limits established by agreement with the Nevada Division of Environmental Protection for each analyte. These data indicate that there has been no measurable impact to the uppermost aquifer from the Area 5 RWMS. There were no significant changes in measured groundwater parameters compared to previous years. The report contains an updated cumulative chronology for the Area 5 RWMS Groundwater Monitoring Program and a brief description of the site hydrogeology.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

International Good Practice in Preparing for Decommissioning - 18404

The transition of a nuclear facility from operation to the implementation of dismantling is a critical phase in every decommissioning project. Several organizational and technical modifications are needed to adapt the facility to meet the new objectives and requirements. A variety of activities need to be planned and performed to support the transition and to prepare the dismantling of the facility. Experience has shown that it is essential to start with preparations for decommissioning at a very early stage, at best already during the design stage of the facility but at least during the operational stage. The preparation of the transition for decommissioning and dismantling (D and D) is a key issue for the success of the global D and D project to minimize delays and undue costs; to optimize personnel and other resources; and to initiate preparatory activities for decommissioning in a planned, timely and cost-effective manner and thus to ensure safe and efficient decommissioning. With the growing number of nuclear facilities reaching the decommissioning stage, the Working Party on Decommissioning and Dismantling (WPDD) within the Nuclear Energy Agency of OECD formed the Task Group on Preparing for Decommissioning. This group of experts include regulators, nuclear operators and independent experts to review the strategic aspects to optimize the preparations for decommissioning from the last years of operation onwards. This paper gives and overview of the work carried out by TGPFD between 2015 and 2017 and covers strategic approaches, issues and risks and observations of good practice rather than providing detailed descriptions of methods or technologies. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗