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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 721 records · Page 40
All sourcesNASA NTRSDOE OSTI
DOE OSTI2013

Study on Shielding Requirements for Radioactive Waste Transportation in a Mo-99 Production Plant - 13382

Brazil is currently planning to produce {sup 99}Mo from fission of low enriched uranium (LEU) targets. The planned end of irradiation activity of {sup 99}Mo is about 185 TBq (5 kCi) per week to meet the present domestic demand of {sup 99m}Tc generators. The radioactive wastes from the production plant will be transferred to a waste treatment facility at the same site. The total activity of the actinides, fission and activation products present in the wastes can be predicted based on the yields of fission and activation data for the irradiation conditions, such as composition and mass of uranium targets, irradiation time, neutron flux, production schedule, etc., which were in principle already established by the project management. The transportation of the wastes from the production plant to the treatment facility will be done by means of special shielded packages. An assessment of the shielding required for the packages has been done and the results are presented here, aiming at contributing to the design of the waste management facility for the {sup 99}Mo production plant. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

The Potential NCS issue process - A method to screen emerging issues

The Potential NCS Issue (PNI) Process is a newly developed methodology that allows for the screening of new information potentially adverse to nuclear criticality safety. The PNI Process allows for transparency of possible emerging issues with both contractor management and on-site regulators. Sources of PNI include the -1) discovery of potential errors, inaccuracy, or omission in an effective criticality safety evaluation, -2) field conditions not accounted for in an effective evaluation, and -3) a potential inadequacy in a supporting calculation. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Lessons Learned From Decommissioning B411 Decontamination Centre at Whiteshell Laboratories - 18211

Whiteshell Laboratories, located in Manitoba, Canada, provided research facilities for the Canadian nuclear industry since the early 1960's. The facility was centered on the largest organically cooled, heavy water moderated nuclear reactor in the world, the WR-1. It is now operated by Canadian Nuclear Laboratories (CNL) and is the first major decommissioning project of a nuclear research establishment in Canada. One of the major projects to support the closure of Whiteshell Laboratories (WL) is the decommissioning and demolition of the Building 411 (B411) Decontamination Centre, which provided a decontamination service for maintaining research and development of experimental rigs, equipment and tools in a safe usable state. It also provided a laundry service for radioactively contaminated clothing. The team successfully self-performed their first demolition of a nuclear facility, but not without challenges. The baseline decommissioning strategy assumed most of the facility would meet unconditional clearance levels; however when characterization revealed the extent of contamination exceeded initial assumptions projected from process knowledge, in conjunction with resource challenges and a waste disposal pathway not firmly established, active remediation of the facility was undertaken. With an unknown waste acceptance criteria for the future waste disposal facility, sludge that had accumulated in a tank used to collect xylene and organic coolant from contaminated tools and equipment and the selection of appropriate waste packages for waste storage, transportation and disposal forced the project team to adjust their demolition timeline. This, coupled with developing an open air demolition plan and managing an uncertain end state criteria, were just some of the major tasks the team successfully navigated. The impact on both schedule and cost performance caused by the change in strategy, and the lessons learned experienced by the WL Decommissioning Project Team that are being applied as the Whiteshell Laboratories Closure Project (WLCP) moves forward with the next major decommissioning challenge, are highlighted in this paper. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Panel Session 26: Risk-Based Approaches to Environmental Remediation and Adaptive Site Management

This panel discussed the needs and importance of developing risk-based approaches to environmental remediation that will enable complex sites to be adaptively managed by applying cost-effective remedies that are protective of human health and the environment. The discussion emphasized risk-based approaches within decision processes and subsequent incorporation into regulatory decision documents. Remedy approaches, remediation exit strategies, and long-term monitoring plans that support risk-based end-states for difficult-to-remediate sites were discussed Panelists with presentations: Risk-Informed Approaches to Environmental Remediation and Adaptive Site Management (Vicky Freedman); ITRC Adaptive Site Management Perspective (Michael Truex); Optimization During Operations and Maintenance Phase at the Hanford Site 200-ZP-1 Groundwater Operable Unit (Emerald Laija, Kate Amrhein, Michael Truex); Adaptive Management: EPA Overview (Benjamin Simes); Decommissioning and Environmental Remediation Section Division of Nuclear Fuel Cycle and Waste Technology (Horst Monken Fernandes)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Cigeo Design Options, Risks and Opportunities Management: A Continuous Project Management Goal - 20015

Andra is currently completing the detailed engineering phase of the stepwise design development of Cigeo, the French HLW and IL-LLW Deep Geological Repository. If licensed in the coming years, Cigeo's progressive construction, industrial operation and closure will last over more than a century. Such a duration, associated with the requirements in terms of reversibility, lead to the choice of an incremental design that allows, for next operator generations, to integrate improvements derived from scientific and technical progress as well as from experience feedback from its operation. This incremental design approach, associated with a permanent risks and opportunities management process, will continue after licensing of Cigeo as a tool for the governance of the reversibility. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Research Campus Energy: I2SL China

Presentation offers an overview of energy-efficient research campuses, including the benefits, the program, and what it takes to develop one.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗
DOE OSTI2015

Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

Development of evaluation models of manpower needs for dismantling the dry conversion process-related equipment in uranium refining and conversion plant (URCP)

Evaluation models for determining the manpower needs for dismantling various types of equipment in uranium refining and conversion plant (URCP) have been developed. The models are widely applicable to other uranium handling facilities. Additionally, a simplified model was developed for easily and accurately calculating the manpower needs for dismantling dry conversion process-related equipment (DP equipment). It is important to evaluate beforehand project management data such as manpower needs to prepare an optimized decommissioning plan and implement effective dismantling activity. The Japan Atomic Energy Agency (JAEA) has developed the project management data evaluation system for dismantling activities (PRODIA code), which can generate project management data using evaluation models. For preparing an optimized decommissioning plan, these evaluation models should be established based on the type of nuclear facility and actual dismantling data. In URCP, the dry conversion process of reprocessed uranium and others was operated until 1999, and the equipment related to the main process was dismantled from 2008 to 2011. Actual data such as manpower for dismantling were collected during the dismantling activities, and evaluation models were developed using the collected actual data on the basis of equipment classification considering the characteristics of uranium handling facility. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

The DISTINCTIVE University Consortium: AGR, Magnox and Exotic Spent Fuels - 18345

The Engineering and Physical Sciences Research Council (EPSRC) sponsored consortium Decommissioning, Immobilisation and Storage Solutions for Nuclear Waste Inventories (DISTINCTIVE) is contributing to the development of skilled cross-disciplinary scientists and engineers with the knowledge and experience required to develop engineering solutions tailored for application within radiologically contaminated sites. Of the four themes addressed by the DISTINCTIVE consortium, the AGR (Advanced Gas-Cooled Reactor), Magnox and Exotic Spent Fuels theme considers the UK's diverse spent nuclear fuel inventory and the preferred options for disposal; this includes the retrieval of fuel from current storage facilities and the repackaging options available. Specifically, the research is concerned with AGR, Magnox and so-called 'Exotic' spent fuels; the goal being to increase knowledge and mechanistic understanding of the processes affecting long-term management and mitigation of any potential risks. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Delivering Business Benefit to UK Decommissioning through Collaborative Innovation - Approach and Technologies - 18539

The UK's nuclear energy programme, dating from the post-war years, has left a mixed legacy to the country: numerous prototype reactors, fuel-manufacturing plants, research centres, reprocessing plants and 11 power stations. The Sellafield site in west Cumbria houses more than 200 nuclear facilities and 1,000 buildings, making it one of the world's most complex environmental decommissioning challenges. Many 'never-done-before' projects are under way, which require substantial levels of R and D and innovative engineering approaches. One of the Nuclear Decommissioning Authority's (NDA) responsibilities is to ensure that the right level of R and D is carried out to enable progress on delivering the full decommissioning programme. Since 2010, NDA has been collaborating with Innovate UK, the UK government's innovation agency, to engage the supply chain and develop innovative technologies and services to support the NDA's mission and the growing international nuclear decommissioning market. The paper will provide an overview of the approach (e.g. open calls, briefing events, independent assessment, technology showcases) and the associated benefits (e.g. attracting new ideas, end-user engagement, increased supply chain collaboration). The paper also highlights selected technologies developed through the process. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Fit for Purpose Remote Technology Decommissioning Solutions - 18630

The Magnox Decommissioning Project is actively progressing clean-up and decommissioning of 12 reactor sites across England, Scotland and Wales. Funded and directed by the United Kingdom's Nuclear Decommissioning Authority (NDA) and managed by the Cavendish Fluor Partnership (CFP), the Magnox Decommissioning Project introduces a wide range of radiological and industrial hazards warranting deployment of remote technologies to safely de-inventory, decontaminate and decommission a vast array of nuclear facilities. The Magnox Decommissioning Project encompasses 22 former Magnox nuclear power production reactors across 10 reactor sites and five research/test reactors at two former research sites. Decommissioning activities have been underway at some sites for nearly 20 years with early focus on retrieving and stabilising wastes and draining and stabilising spent fuel ponds. The Magnox decommissioning strategy invokes a programme perspective to drive consistency in tackling similar decommissioning and waste challenges across multiple sites. Programme central teams have worked with technology suppliers to foster learning from industry experience to develop and deploy tooling and robotics. The programme approach has also facilitated learning from one site to the next. In many cases, this central programme approach has promoted an evolution of technologies resulting in optimisation of simple remote tooling. In other instances, collaboration with suppliers is producing state-of-the-art technologies to tackle more unique challenges including, most recently, early demonstration of laser cutting for reactor vessel dismantling. This paper will outline the programme management approach and the scalable optioneering process Magnox employs to select the engineered controls and technologies used in decommissioning and waste management activities. It will provide an overview of the broad range of remote tooling and robotics deployed across the 12 Magnox sites by exploring some specific examples. Lastly, the paper will summarise key lessons learned in the now extensive history of selecting and using remote technologies to decommission Magnox nuclear facilities. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Safely Managing CNL's Shutdown Prototype Power Reactors - 30 years of Experience - 19157

Canadian Nuclear Laboratories (CNL) has over 30 years of experience managing three prototype power reactors from shutdown through storage with surveillance and into preparation from final decommissioning. CNL is responsible for the safe storage with surveillance of three prototype power reactors; Nuclear Power Demonstration (NPD), Gentilly-1(G1) and Douglas Point (DP). Each of the Canadian prototype power reactor sites have been maintained using different post shutdown management strategies, which were based on the site location, configuration, and intended designation of the respective sites. This paper will discuss the post shutdown strategies employed at the three sites, including details of their shutdown strategy, current conditions, and experience gained from the period of storage with surveillance. (author)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Latest Developments in PM Systems and Methods and their Application to WM Projects - 20364

How do you improve on an industry that is well established yet often misses the mark on key metrics demonstrating effective planning and execution of project scope, schedule and budget? With the increased complexity of DOE projects relative to either poorly kept records of what wastes are stored or the lack of specific knowledge relative to the waste concentrations/quantities, this is a question continually asked and investigated by many. In fact, in 2017, the GAO's report to Congress indicated that although the DOE has made some progress on its monitoring effectiveness and demonstrating progress criteria, these goals were not met and there needs to be more improvement and monitoring. This paper will offer some insights into the latest developments in project management methodologies and the possible application of these to waste management projects. Traditional data generated via a project schedule that utilizes critical path methodology (CPM) and additional earned value management (EVM) data needs to be accurate and enable the project manager to better understand the probability of project success. Although this data has readily been available on most large-scale projects, success as measured by various stakeholder groups including the client, project team, regulators, etc. is less than optimal. Therefore, an urgent need exists to explore how traditional project data (CPM and EVM) coupled with new methodologies allows for better planning and execution by the project team. Many new approaches/methodologies can even be used to predict the success of options prior to full implementation on the actual project. Three approaches/methodologies will be discussed: - Artificial Intelligence; - Change Management; - Blend of Traditional Management (Gantt chart) and Agile Methodologies. As market forces change, so will the direction of project management. The days of 'one size fits all' are no longer valid. A combination of predictive and adaptive approaches in the management of projects is essential to enable execution of project deliverables on time, under budget, and within the contractual scope. This paper is intended to provide the reader with insight to the close relationship of project management trends and business management trends, and to provoke critical thinking about what it means to align project management strategy with an environment of non-stop innovation. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

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↗
DOE OSTI2019

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↗
DOE OSTI2018

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↗
DOE OSTI2019

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↗
DOE OSTI2017

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↗