Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Restructuring”

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.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 577 records · Page 32

xSDK: Building an ecosystem of highly efficient math libraries for exascale

Current efforts to build increasingly powerful computer architectures are opening up new avenues for more complex and higher fidelity simulations coupled with data analytics and learning, leading to new scientific insights and deeper understanding. At one extreme, exascale computers will be much faster than previous computer generations (performing 10 18 operations per second—that is, 1,000 times faster than petascale). To achieve these performance improvements, computer architectures are becoming increasingly complex, with deep memory hierarchies, very high node and core counts, and heterogeneous features such as graphics processing units (GPUs). Such architectural changes impact the full breadth of computing scales, as heterogeneity pervades even current-generation laptops, workstations, and moderate-sized clusters. While emerging advanced architectures provide unprecedented opportunities, they also present significant challenges for developers of scientific applications, such as multiphysics and multiscale codes, who must adapt their software to handle disruptive changes in architectures and new programming models that have not yet stabilized. Developers must consider increasing concurrency while reducing communication and synchronization, and other complexities such as the potential for using mixed precision to leverage the compute power available in low-precision tensor cores. On one hand, developers must implement new scientific capabilities, which in turn increase code complexity. On the other hand, the codes must be ported to new architectures, requiring the inclusion of new programming models and the restructuring of code to achieve good performance. Addressing these issues is beyond the capability of any single person or team—leading to the need for collaboration among many teams, who encapsulate their expertise in reusable software and work together to create sustainable software ecosystems.

97 MATHEMATICS AND COMPUTING↗

Performance Assessment of OpenMP Compilers Targeting NVIDIA V100 GPUs

Heterogeneous systems are becoming increasingly prevalent. In order to exploit the rich compute resources of such systems, robust programming models are needed for application developers to seamlessly migrate legacy code from today’s systems to tomorrow’s. Over the past decade and more, directives have been established as one of the promising paths to tackle programmatic challenges on emerging systems. This work focuses on applying and demonstrating OpenMP offloading directives on five proxy applications. We observe that the performance varies widely from one compiler to the other; a crucial aspect of our work is reporting best practices to application developers who use OpenMP offloading compilers. While some issues can be worked around by the developer, there are other issues that must be reported to the compiler vendors. By restructuring OpenMP offloading directives, we gain an 18x speedup for the su3 proxy application on NERSC’s Cori system when using the Clang compiler, and a 15.7x speedup by switching max reductions to add reductions in the laplace mini-app when using the Cray-llvm compiler on Cori.

Davis, Josh↗

Recent Hydrodynamic Modeling Enhancements in OpenFAST: Preprint

To improve the hydrodynamic modeling capabilities of the offshore wind design and modeling tool OpenFAST, a restructuring of the HydroDyn hydrodynamics module was undertaken with several new features implemented. The generation of the wave field is now separated from HydroDyn into a new module called SeaState. Unlike previous versions of HydroDyn, which precomputed the wave kinematics at the undisplaced positions of the hydrodynamic nodes, the new SeaState module computes the complete time history of the wave field at the vertices of a user-defined wave grid. During the simulation, the wave kinematics at any point within the grid can be efficiently interpolated, allowing the strip-theory wave loads to be evaluated based on the wave kinematics at the displaced structure position. A phase correction was also implemented for the potential-flow wave-exciting loads to account for large structure displacements. Several wave-stretching methods were implemented for the strip-theory solution along with a wave-load redistribution method that ensures smooth variation of the nodal loads as the nodes of a discrete hydrodynamic mesh enter and exit the water. The load smoothing is included to avoid the excitation of unphysical high-frequency structural vibration during hydroelastic simulations. The MacCamy-Fuchs diffraction correction for the strip-theory solution and the capability to insert a constrained NewWave into extreme stochastic sea states with directional spreading were also added. The present article documents the formulations of the new improvements to HydroDyn with example applications and numerical results.

constrained wave↗

Fort Erie Case Study - Transition from Fixed-Route to On-Demand Transit

Rural and smaller-sized communities in North America face unique mobility challenges due to their low population density, lower public transit spending per capita compared to major cities, and a high reliance on private vehicles. In recent years, communities such as Fort Erie, Ontario, have restructured or advanced their public transit systems using on-demand services. Fort Erie is a relatively sparsely populated region of 32,901 residents, spread across a land area of 166 square kilometers (64 square miles), for an average population density of 193 residents per square kilometer (500 per square mile). In October 2021, the town implemented a mobility-on-demand system integrated with smartphone software to replace its fixed-route community bus system, which consisted of four buses with three routes, each with a roughly 1-hour, one-way loop. The new service utilizes a fleet of six minivans, two of which are retrofitted with wheelchair-accessible ramps. The system may require that a passenger requesting a standard van walk up to 400 meters (a quarter mile) to their pickup location to optimize vehicle routing while providing origin-to-destination service. The on-demand system proved effective in providing service, eclipsing pre-pandemic ridership by 40%, decreasing greenhouse gas emissions per ride by 63%, and decreasing the cost to the town per ride by 29%. This report documents both the previous system and the new system in terms of routes, ridership, costs, fuel, and other notable system parameters. This work is part of an ongoing series of case studies on providing small communities with on-demand, right-sized vehicle service coupled with a smartphone application.

ADVANCED PROPULSION SYSTEMS,ENERGY PLANNING, POLIC↗

A Program Analysis Tool to Query Static and Dynamic Characteristics of HPC Applications

Emerging HPC platforms are becoming extraordinarily difficult to program as a result of complex, deep and heterogeneous memory hierarchies, heterogeneous cores, and the need to divide work and data among them. New programming models and libraries are being developed to aid in porting efforts of application developers, but substantial code restructuring is still necessary to fully make use of these new technologies. To do this effectively, these developers need information about their source code characteristics, including static and dynamic (e.g. performance) information to direct their optimisation efforts and make key decisions. On the other hand, system administrators need to understand how users are using the software stack and resources on their systems to understand what software they need to provide to improve the productivity of the users on a platform.In this paper we describe a tool that combines compiler and profiler information to query performance characteristics within an application or across multiple applications on a given platform. Static and dynamic data about applications are collected and stored together in an SQL database that can be queried by either a developer or a system administrator. We will demonstrate the capabilities of this tool via a real-world example from application-driven case studies that aims at understanding the use of scientific libraries on a routine from the molecular simulation application CP2K.

Welch, Aaron↗

A History of the Environmental Management Advisory Board: 20 Years of Service and Partnership - 13219

The Environmental Management Advisory Board (EMAB or Board) was chartered under the Federal Advisory Committee Act (FACA) in 1992 to provide the Assistant Secretary for Environmental Management (EM) with independent and external advice, information, and recommendations on corporate issues relating to accelerated site clean-up and risk reduction throughout the EM complex. Over the course of the past 20 years, the composition and focus of the Board have varied widely to address the changing needs of the program. EMAB began as the Environmental Restoration and Waste Management Advisory Committee, formed to provide advice on an EM Programmatic Environmental Impact Statement. In 1994, the Board was restructured to function more as an executive-level, limited member advisory board whose membership provides insight of leading industry experts and the viewpoints of representatives from critical stakeholder constituencies. Throughout the 20 years of its existence, EMAB has covered a wide variety of topics and produced nearly 200 recommendations. These recommendations have resulted in several policy changes and improvements within EM. Most recently, EMAB has been credited for its contribution to the EM Energy Park Initiative, forerunner of the DOE Asset Revitalization Initiative; creation of the EM Offices of Communications and External Affairs; improvement of acquisition and project management strategies and culture; and several recommendations related to the Waste Treatment Plant and the tank waste programs at Hanford and the Savannah River Site. The wealth of experience and knowledge the Assistant Secretary can leverage through utilization of the Board continues to support fulfillment of EM's mission. In commemoration of EMAB's 20. anniversary, this paper will provide further context for the evolution of the Board, the role FACA plays in its administration, and a look at the members' current objectives and EM's expectations for the future. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Synchrotron XRD analysis of irradiated UO{sub 2} fuel at various burn-up

The micro-XRD technique based on synchrotron radiation is a powerful tool to analyze subtle changes in the crystal lattice structure of irradiated nuclear fuels. The micrometric beam size probes a relatively small volume in the samples. This, in turn, can allow studying the evolution of the material with burn-up even at the level of the grain sizes of the fuel. We report here the results obtained by micro-XRD performed at the microXAS beamline of the Swiss Light Source (SLS) on the two end-members of a series of burn-ups, i.e. a fresh non-irradiated UO2 (reference sample) and a 9 cycle sample, plus the first results on 5- and 7 cycle fuels. The use of the micro-beam allows us to follow the extent of grain polygonization as a function of burn-up and in a lower degree of temperature. The microXAS beamline being the only one where series of spent fuel are investigated, the current results presented in this study are of unique value. In earlier work at lower burn-ups and for doped fuel it has been shown that there is a strong difference in polygonization between center and periphery. While for the 9-cycle a complete restructuring could be shown here, the results for the 5- and 7-cycle samples are not fully conclusive. We obtain interesting results for these samples where both center and the periphery regions exhibit a mix of XRD reflexes, indicating various stages of sub-grain formation. Further detail analyses are needed on the basis of the numerous 2D XRD pictures captured to gain a clearer picture.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Mu2e - Research & Development

Current efforts are being conducted at Fermi National Laboratory to study potential violations in accepted theory that would otherwise suggest a restructuring of our fundamental understanding of the universe. Mu2e is one of these frontier projects that studies Charged Lepton Flavor Violation (CLFV) which if observed, would suggest physics beyond the Standard Model. Therefore, this note encompasses several projects that contribute to the fruition of Mu2e investigations. Due to the broad range of disciplinary inconsistencies that each project requires, all the work is being presented as a means of justifying contribution to Mu2e. The projects are comprised of a simulation exploring the extinction level of proton pulses after Recycler ring re-bunching by using G4beamline to simulate an 8GeV proton beam interaction with a titanium target, three Cherenkov radiation-based detectors and 2/3-fold and 3/3-fold coincidence rate analysis. Additionally, supplemental work for the implementation of a Micro Telecommunications Computing Architecture (TCA) crate to establish a peak finding algorithm to ensure that the out-of-time beam is less than 10$^{−10}$ fractional level along with single-layer inefficiency analysis on scintillation counters for the Cosmic-Ray Veto (CRV) analysis to ensure the overall inefficiency is 10$^{−4}$. Preliminary results have been achieved for the G4beamline simulation 2/3-fold and 3/3-fold coincidences which are in the order of 10$^{−9}$ and 10$^{−10}$, respectively. Only preliminary results of a triangular counter and four rectangular di-counters for the CRV have been realized. The microTCA crate development is still ongoing.

43 PARTICLE ACCELERATORS↗

Anticipating Change - A Means to Save Time and Rethink the Implementation of the 10 Code of Federal Regulations 770 Real Property Transfer Process - 15662

The Department of Energy (DOE) issued 10 Code of Federal Regulations (CFR) 770 in 2000 for the 'Transfer of Real Property at Defense Nuclear Facilities for Economic Development'. The rule was issued in order to 'offset negative impacts on communities caused by unemployment from related DOE down-sizing, facility close-outs and workforce restructuring'. There is a sense of urgency implied in efforts designed to address economic conditions, especially in communities that have hosted DOE facilities and are experiencing negative impacts of mission changes. Despite the urgency, the transfer of real property from DOE or any federal agency is a lengthy, complex, iterative, but necessarily diligent effort. After all, the aim of the process is to be able to demonstrate that the property proposed for transfer is protective of human health and the environment for the intended use. Notwithstanding the efforts of the economic development organization to market, recruit, and prepare a robust proposal to request property, and the efforts of DOE to perform the many due diligence activities in response to that request, the actual results of the evaluations are an unknown until a major portion of the process is completed. Will the property be determined to be suitable for transfer? Will there be deed restrictions? Is indemnification available? Has a mission need for the property arisen while working through the reviews? There are many points along the way that can sidetrack or delay progress and, in the interim, the economic viability of the proposal can collapse. Even without the unforeseen events, the process in and of itself is lengthy. It is often heard (loudly) that it takes far too long to obtain a piece of property once a request is made; that observation/criticism is worthy of serious attention. Rather than revisit old debates, why not learn from them? Why not look at the transfer process from a different point of view and ameliorate it so it can be more responsive to community needs? Why not anticipate change, anticipate requests, and make property available before a request as well as responding to requests to make property available? There are several ways to rethink and modify the way the transfer process is implemented to reduce the time following a request. The modifications would arise from both internal information sharing, integrated and timely up-front planning and, in particular, by varying how and when certain elements of the process to enable transfer are performed. This paper will address: 1. How a unified overall vision can be created from the cleanup input of Site-Specific Advisory Boards with the Community Reuse Organizations' planning for economic development and can help inform site cleanup to end state to future use; 2. Why DOE is in the best position to know its site conditions and could determine ahead of a transfer request what property is indeed available and notify of that determination; 3. How a range of disposition paths for real property are available to DOE; and 4. Why broadening the understanding of 'best interest of the government' to one that is clearly able to recognize non-monetary benefits is in the best interest of the government. Anticipating change helps prepare DOE and their host communities for the future. It creates opportunities for flexibility and time savings. The sooner DOE's unneeded and under-utilized real property can be made available to the communities that need it most, the sooner those communities can work to moderate the adverse effects of DOE mission changes. (author)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Canada's Nuclear Legacy Liabilities Program - Ten Years of Progress and Achievements - 16456

Nuclear legacy liabilities have resulted from more than 60 years of nuclear research and development carried out on behalf of Canada. The liabilities are located at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories in Ontario and Whiteshell Laboratories in Manitoba, as well as three shutdown prototype reactors in Ontario and Quebec that are being maintained in a safe storage state. Estimated at about $10.6 billion (B) (current day Canadian dollars), these liabilities consist of disused nuclear facilities and associated infrastructure, a wide variety of buried and stored waste, and contaminated lands. The Government of Canada established the Nuclear Legacy Liabilities Program (NLLP) in 2006 to implement a long-term strategy to safely and cost-effectively reduce risks and liabilities, and invested approximately $1.4 B over the 10-year duration of the Program to implement the strategy. Risks and liabilities were reduced through projects and activities that decommissioned and removed out-dated facilities, remediated lands affected by past practices, and improved the management of legacy radioactive waste. The NLLP formally ended in September 2015 when the restructuring of AECL's Nuclear Laboratories was completed, and a Government-owned Contractor-operated (GoCo) management model came into effect. The nuclear decommissioning and waste management work that was previously carried out under the NLLP was transitioned into the new GoCo contract. Over the 10-year duration of the NLLP, the Program achieved good progress in addressing health, safety and environmental priorities, reducing liabilities, and providing the studies, plans and facilities that will be needed to enable subsequent phases of the strategy. The NLLP provided a strong basis for the GoCo contractor to accelerate risk and liability reduction at AECL sites. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Regulation of the Shutdown Defueling and Decommissioning Reactors in the United Kingdom - 16576

Nuclear policy, including for decommissioning, in the United Kingdom is set by the UK Government. The Nuclear Decommissioning Authority, NDA, is responsible for managing the clean-up of the UK's nuclear legacy which includes the first generation of Magnox power stations. Magnox Ltd (MXL), owned by Cavendish Fluor Partnership, is the licensee and the management and operations contractor responsible for ten Magnox reactor sites and two restoration sites in the UK, working for the sites' owner, NDA. The work of the company is diverse covering electricity generation at Wylfa (until December 2015), defueling, and preparation for an interim end state, known as Care and Maintenance (C and M) which will precede the final site clearance. The C and M phase is expected to last over 75 years during which the sites are maintained in a passively safe and secure state while radiation levels are left to decay naturally. Preparations for this phase include removing fuel from the reactors and storage ponds; retrieving intermediate level waste from current stores and treating it or converting it to forms suitable for long-term storage or disposal and making sure of the integrity of critical safety systems of the de-fuelled reactors. The Decommissioning, Fuel and Waste programme within the Office for Nuclear Regulation, ONR, regulates nuclear safety in the 12 Magnox nuclear licensed sites. ONR works with the environmental regulators who are responsible for environmental protection on nuclear sites. The focus of this paper is the regulation of nuclear safety by ONR across the Magnox sites and the interactions with nuclear security and the environmental aspects required to achieve effective, proportionate and efficient regulation of these sites in the UK. ONR's strategy for regulating the Magnox defueling and decommissioning sites is focused on enabling the licensee to complete the initial stages of decommissioning and reduce the nuclear and radioactive hazards on its sites. To this effect, ONR's revised inspection guidance is centred on inspecting the (remaining) important systems for safety identified in the safety cases. Other interventions focus on engaging with the licensee on safety significant decommissioning projects to gain evidence of the licensee's readiness prior to and during these activities rather than formal assessment of the associated safety cases. In light of reduced hazards and risks across the de-fueled and decommissioning Magnox reactors, ONR's revised regulatory expectation regarding evolution of emergency arrangements during decommissioning is based on key transition points that follow electricity generation. Implementation of these revised strategies as well as organisational restructuring within the team responsible for regulation of the Magnox fleet has resulted in improved efficiency and consistency in regulatory approach whilst securing the required safety standards in managing decommissioning activities. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Retrieval project Asse II - Lessons Learned in Radiological Protection - 18263

From 1967 to 1978 in total 125,787 drums and packages with low- and intermediate level waste were emplaced in the Asse II mine. The disposal operation ended in 1978 due to a revision of the Atomic Energy Act. For the disposal of radioactive waste, a plan approval procedure would have been mandatory due to the Atomic Energy Act, but the mining law was the legal basis for operating the Asse II mine, further on. A concept for a closure of the mine was not existing at that time. On January 1, 2009, the Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz BfS) became the new license-holder and operator of the Asse II mine under the Atomic Energy Act. The Act on the Organizational Restructuring in the Field of Disposal in Germany became effective on July 30, 2016. The act provides that a federally owned company, the Bundesgesellschaft fuer Endlagerung (BGE mbH, Federal Company for Radioactive Waste Disposal) is formed to carry out the operative tasks of searching for a High Level Waste (HLW) repository, the construction and operation of repositories (Konrad, Morsleben) and of the Asse II mine. Since April 25, 2017 BGE is in charge of the operative tasks that have so far been carried out by BfS. Up to now, the long-term safety of the Asse II mine has not been demonstrated in the case that all the waste will remain inside the mine. Further problems arise from a lack of host rock stability, the incomplete backfilling of the mining areas that have not been used for the emplacement of radioactive waste, and a continuous brine inflow into the mine of approx.12 m{sup 3} per day. For these reasons, according to chap. 57b of the Atomic Energy Act, the Asse II mine is to be closed without delay after retrieving the emplaced nuclear waste. Besides the recent organizational changes in Germany and the special problems giving rise to retrieve the waste, in this paper the operational experiences since 2009 on the way from mining law to atomic law will be described. This applies to the radiation protection regime, the release and clearance procedure, and some measures to boost efficiency. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Revenue Opportunities through Ancillary Services for Nuclear Power Plants with Integrated Firebrick Resistance- Heated Energy Storage (FIRES)

Deregulation of electricity markets has brought about major changes in the ways investments in and operation of power plants are planned and optimized. Although many NPPs have seen reduced revenue in recent years as power purchase agreement end and wholesale market electricity prices have remained low, there are opportunities to expand the technical capabilities of NPPs, participate in additional market services and increase revenue. This transaction summarizes the opportunities provided by participation in ancillary services markets potentially made possible by integration of thermal energy storage capacity, specifically the Firebrick Resistance-heated Energy Storage System (FIRES), into future nuclear power plants with high-temperature reactors and Nuclear Air-Brayton combined cycle (NACC) power conversion. The restructuring, or deregulation, of electric power systems in most of Europe and North America has had a substantial impact on the economic performance of currently operating nuclear power plants (NPPs) and the prospects for new builds. Owners of NPPs in some markets have expressed concern that low wholesale electricity market prices and insufficient compensation for capacity, reliability, and other services are threatening the financial viability of their plants. However, both current and future NPPs have the potential to increase their competitiveness by increasing the flexibility of their electricity output. Flexible output has previously only been possible in water-cooled reactors through load-following operation, which requires core power maneuvers and operation of the steam turbine at reduced efficiency. Integration of thermal energy storage systems (TESS) provides an alternative, providing the plant the option to either output electricity or store heat for greater later electric output. The plant owner may thus increase sales of electricity during hours when it is most valuable. Even more, some TESS technologies have the potential to greatly increase the net ramp rate capability of the plant. The ability to rapidly change net power output to the grid may make it possible for NPPs to secure additional revenue by providing additional minute-by-minute balancing services to the grid. FIRES is only one technology out of many that might provide additional technical capabilities at NPPs, and this discussion has only highlighted the opportunities in a single market. Analysis of other options, include steam accumulator systems, nitrate salt TESS, phase change material TESS, and opportunities in other markets are subjects of ongoing work. Deregulation of electricity markets has brought about major changes in the ways investments in and operation of power plants are planned and optimized. Although many NPPs have seen reduced revenue in recent years as power purchase agreements end and wholesale market electricity prices have remained low, there are opportunities to expand the technical capabilities of NPPs, participate in additional market services, and increase revenue. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Synthesis and Characterisation of Nanostructured UO{sub 2} Compacts for Separate Effect Investigations

At high burn up nuclear fuel undergoes a significant restructuring, and in particular near the pellet edge, where large 10 μm UO{sub 2} grains of the fresh fuel fragment to yield a material with grain size of 100-300 nm and porosity up to 20%. This so-called 'High Burn up Structure (HBS)' has been investigated in the past to elucidate its morphology, grain size, crystal structure, thermal conductivity, hardness, etc.. Handling of spent fuel, however, is difficult due to its high radioactivity and the concomitant shielding needed to manipulate even the smallest samples. The establishment of a route to prepare a surrogate material closely mimicking the HBS morphology is an essential step, if all the details of this fascinating material are to be understood. Furthermore, preparation of dense bulk nanocrystalline UO{sub 2} as a function of grain size and porosity enables the effect of these crucial parameters to be distinguished, ultimately to provide a full insight into properties of HBS and their detailed assessment. We have successfully produced high density UO{sub 2} disks (φ = 4 mm, h= 1 mm) with grain sizes tunable in the 40 to 1000 nm range, from 10 nm UO{sub 2} powders generated by oxalate precipitation of UO{sub 2} from U(IV) solutions. Consolidation has been achieved using a specially constructed spark plasma sintering (SPS) unit housed in a radiological glovebox, which is equipped with a special die system incorporating SiC inserts to achieve pressures of 500 MPa. The latter innovation has reduced processing times and temperatures, which in turn limits grain growth, but still enabling fully dense compacts to be produced. These results now open the path to determine the potential effect of grain size on mechanical properties, thermal conductivity, irradiation damage (and its recovery), and gas (fission and helium) behaviour therein. Furthermore, using suitable pore formers, samples with controlled porosity to fully emulate the HBS in irradiated fuel can be prepared. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

The German Site Selection Process - Implementation and Challenges - 20528

Federal Company for Radioactive Waste Disposal (Bundesgesellschaft fuer Endlagerung mbH; hereinafter referred to as BGE) is a state-owned company established in September 2016 following the 'Act on the Organisational Restructuring in the Field of Radioactive Waste Storage'. 'Repository Site Selection Act' (hereinafter referred to as StandAG) defines the site selection procedure, aiming to ensure the best possible safety for storing high-level radioactive waste in Germany for the duration of one million years. The selection procedure is a participatory, transparent, learning and self-questioning process based on scientific expertise. Possible repository sites are sought all over Germany, without excluding or predetermining any potential site at the beginning. The procedure consists of three phases. After each phase, the legislative decides on the regions for further consideration in the next phase of the site selection procedure. The current first phase (Phase I) is divided into two steps. Objective of Step 1 is to determine subareas of favorable geological conditions based on available data. Step 2 of Phase I will lead to identification of specific regions that are considered for further surface-based geoscientific and geophysical exploration. Potential host rocks are rock salt, clay rock and crystalline rock. As part of the site selection procedure, an overview of the status of the planning and implementation of R and D activities is given. Topics of particular interest are, for example, the adaptation of the maximum temperature of 100 deg. C at the container surface, the impact of long-term climate variations as well as minimally invasive exploration methods. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

NBSR reactor control room upgrade - 215

The maintenance and modernization of the National Institute of Standards and Technology (NIST) Center for Neutron Research (NCNR) reactor, known as the NBSR, is an ongoing process to endure until the eventual decommissioning of the reactor. As part of the renovation effort, the reactor control system is to be upgraded. Following some initial outsourcing efforts, the NBSR reactor control system upgrade has been restructured to be implemented by in-house means. The beginning stage of the upgrade involved the development of a simulator environment based on a PC system and digitization of the majority of nuclear reactor monitoring data. The NBSR reactor surveillance data consists of approximately thirteen hundred input/output points, including analog/digital sensor signals, signal conditioners, and relay logic. The aim of the current phase is to implement a new reactor data acquisition and display system (RDS) and lay out the infrastructure for the upgrade of the reactor control system (RCS). Key design criteria are to implement a reliable, redundant, diverse, modular and candid system where any complex digital manipulations are taken outside of the control room. Basically, the data analytics and custom codes are separated from reactor operation control and decision making logic. Furthermore, the new RDS is designed such that it could be maintained internally by NCNR personnel. The RDS is unique in design and modularity, minimizing custom codes and testing, making it ideal for research reactors. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Post-Irradiation Examination for Conventional and Advanced Nuclear Fuel

During irradiation in a nuclear reactor, the fuel pellet experiences non-uniform fission rate and strong thermomechanical loads, which result in alterations and restructuring occurring non-homogeneously in the fuel volume. The irradiated fuel is characterized by a highly heterogeneous structure, with a correspondingly heterogeneous distribution of phases and properties. It is a big technical challenge for a hot cell facility to be able to cover effectively a broad variety of fuel types and compounds, characterized by different compositions, physico-chemical properties, geometries and configurations. The first challenge is to provide testing environments and procedures which do not alter or degrade the original irradiated fuel properties and are technically suitable for hot cell or shielded facility operation. For instance, non-oxide fuel compounds require protective atmosphere to avoid sample oxidation during storage, preparation and testing. Moreover, suitable adaptations of tools and measuring devices must be available to characterize fuel configurations which differ from the conventional cylindrical pellet-cladding geometries (e.g. spherical fuel elements for pebble bed HTR and TRISO coated fuel particles). Finally, adequate scientific methods of investigation must be available to measure properties and study the behaviour of highly heterogeneous irradiated fuel. In addition to basic techniques for non-destructive and destructive examination of nuclear fuel systems (e.g. covering fuel and cladding or fuel and coatings, or other configurations), 'in-depth' methods are applied to determine physical, thermomechanical and micro-analytical properties of specific phases/features present in irradiated fuel. This paper presents relevant trends and examples from fuel safety studies performed at JRC-Karlsruhe and in other laboratories which highlight the 'added value' obtainable by applying combined techniques, high resolution tools or 3D methods of analysis for the experimental 'multiscale' characterization of irradiated fuel.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Measurement of Nuclear Power Plant Construction Performance Using EVMS Model

The Earned Value Management System (EVMS) method integrates three critical elements of project management: scope, cost and time management. It requires the periodic monitoring of actual expenditures and physical scope accomplishments and allows calculation of cost and schedule variances along with performance indices. It allows forecasting of project cost and schedule at completion and highlights the possible need for corrective action. Application of earned value management techniques is scalable to individual projects as determined by their size and complexity. Effective management of quality, cost, and time is the utmost objective for any type of construction project. An EVMS model provides an advanced systematic method of controlling these three performance measures in an integrated way. However, the additional management effort required to develop and maintain an effective Work Breakdown Structure (WBS) has been highlighted as a major barrier to application of this concept. This paper examines the influencing attributes that would facilitate effective EVMS implementation including a restructuring of the WBS for nuclear power plant construction.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗