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At least 1,513 records · Page 84

The 2021 Annual CSEWG Meeting at Nuclear Data Week(s)

From November 15-19, 2021, CSEWG held its annual meeting during Brookhaven National Laboratory’s Nuclear Data Week(s)1. The combined event was held via zoom (due to COVID travel restrictions) and there were 175 registered attendees. This was CSEWG’s 3rd fully virtual meeting and, by all accounts, it was a success. The timetable and talks are available at https://indico.bnl.gov/event/13121/overview for registered participants. This meeting began with the welcoming of the new ENDF Library Manager, Gustavo Nobre, the announcement that ENDF/B-VIII.1’s release will be delayed until February 2024 due to COVID induced delays, and the adoption of a draft Code of Conduct. This last point is notable since CSEWG is known for its lively physics and engineering discussions. However, as professionals, we must endeavor to keep our discussions civil, collegial, and inclusive.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Introducing PRIMRE's MRE Software Knowledge Hub (February 2021)

This paper focuses on the role of the Marine Renewable Energy (MRE) Software Knowledge Hub on the Portal and Repository for Information on Marine Renewable Energy (PRIMRE). The MRE Software Knowledge Hub provides online services for MRE software users and developers, and seeks to develop assessments and recommendations for improving MRE software in the future. Online software discovery platforms, known as the Code Hub and the Code Catalog, are provided. The Code Hub is a collection of open-source MRE software that includes a landing page with search functionality, linked to files hosted on the MRE Code Hub GitHub organization. The Code Catalog is a searchable online platform for discovery of useful (open-source or commercial) software packages, tools, codes, and other software products. To gather information about the existing MRE software landscape, a software survey is being performed, the preliminary results of which are presented herein. Initially, the data collected in the MRE software survey will be used to populate the MRE Software knowledge hub on PRIMRE, and future work will use data from the survey to perform a gap analysis and develop a vision for future software development. Additionally, as one of PRIMRE's roles is to support development of MRE software within project partners, a silo of knowledge relating to best practices has been gathered. An early draft of new guidance developed from this knowledge is presented.

gap analysis↗

Updated Waste Management System Analysis Tool Requirements and Enhancements

Draft presentation for presentation to Nuclear Waste Technical Review Board Winter/Spring Meeting March 2nd NOTE: FYI this presentation is almost the same as the presentation that will be uploaded soon entitled 'Next Generation System Analysis Model: Recently Added Features and Future Plans' for the Waste Management 2022 conference.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

U.S. Solar System Decommissioning Policies

In the United States, cumulative installed utility-scale solar photovoltaic (PV) capacity reached more than 60 gigawatts (GW)dc at the end of 2020. Federal and state renewable energy and net-zero emissions policies will continue to drive solar development in the United States with installed utility-scale PV projected to quadruple (240 GWdc) by 2030. Although more than 75% of all U.S. installed utility-scale PV came online in the last 5 years, federal, state, and local governments are planning for system decommissioning. Our research found that as of April 2021, one federal agency, the Bureau of Land Management (BLM), and 15 U.S. states have solar decommissioning policies in place. North Carolina is also in the process of drafting solar decommissioning regulations, and at least 4 states (Maine, Pennsylvania, West Virginia, Texas) proposed solar decommissioning bills in the 2021 legislative session. This presentation looks at U.S. federal and state solar decommissioning policies who they apply to, when they apply, the requirements/responsibilities, and what the impacts are.

circular economy↗

Global Energy Policy to Achieve the United States’ Nationally Determined Contributions: Potential Pathway

In 2021, the United States declared its Nationally Determined Contribution (NDC) in preparation for the COP26 climate summit, setting goals to achieve zero emission electricity by 2035, and reducing net emissions by 50–52% compared to 2005 levels. The current U.S. energy policies were found to not be adequate to meet these goals, thus it is necessary to draft a pathway to achieving these goals through policy changes. This study focused on foreign energy policies to analyze the most effective policies in a host of sectors. By identifying the most ambitious and effective policies from around the world in each sector, this study was able to suggest a policy pathway that can potentially achieve both of goals set in the NDC. In guiding the development of the proposed policy pathway, this study analyzed policies from Australia, Canada, California, China, Denmark, France, Germany, Japan, Russia, South Korea, Sweden, the United Kingdom, and the United States. This study found that the most drastic CO2 reductions came from low-carbon electricity policy, but contributions were also made from carbon capture, reforestation, hydrogen, energy efficiency, and climate smart agriculture.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Projections of Environmental Impacts of Biofuels Across Scenarios Using Prospective LCA

This work showcases a collaboration between leading institutions focusing on integrated assessment modeling (IAM) and life cycle assessment (LCA), sponsored - among others - by the International Energy Agency's Technology Collaboration Program on Bioenergy, Task 45. It presents draft results of a prospective LCA for biofuels across world regions, using regional IAM scenario outputs, and life cycle inventories for country-specific pathways.

bioenergy↗

Summary of Geometric Parameters and Their Effects on Performance of U-10Mo Fuel Plates

A monolithic plate-type fuel system has been under development to convert high-performance test reactors from highly enriched uranium to low-enrichment uranium fuels and is now moving into the qualification phase, a predecessor to the timely conversion of the target reactors. To qualify this fuel system, the plates must meet safety standards and perform well in a reactor. The plates must maintain mechanical integrity, exhibit geometric stability, and have stable and predictable in-reactor behavior. The requirement to maintain mechanical integrity under normal operating conditions is primarily demonstrated by successful testing. However, each high-performance reactor employs a distinct design, resulting in distinct plate geometries, with unique features, attributes, irregularities, and tolerances. Due to the abundance of such distinct geometric varieties, a single “generic” plate geometry capturing all extremes is not achievable. It is also impractical to test each of these proposed designs in a reactor. This limitation necessitates cautious evaluations since the thermomechanical response of a plate with a certain geometry may not be representative for a plate with a significantly different geometry. To address concerns related to in-reactor plate performance, large set of sensitivity studies were performed. These parametric studies aimed to better understand irradiation performance, while evaluating the sensitivity of results to various modeling inputs, including geometric, operational, and material parameters. This work studied selected geometric parameters based on provided fuel specifications and performed a series of parametric simulations. The resulting temperature, displacement, and stress strains were comparatively evaluated to determine the effects of various geometric parameters. This draft provides a “high-level summary” of our parametric sensitivity studies and summarizes the key findings.

42 ENGINEERING↗

APAD for College Credit

Draft Air Permit Applicability Determination (APAD) for Gaseous Hydrogen Supply and Exhaust System for Experiments in TREAT.

99 GENERAL AND MISCELLANEOUS↗

Impact of Lanthanide Complexation and Temperature on the Chemical Reactivity of N,N,N',N'-tetraoctyl diglycolamide (TODGA) with the Dodecane Radical Cation

The impact of lanthanide (Ln) metal ion complexation and temperature on the chemical reactivity of N,N,N',N'-tetraoctyl diglycolamide (TODGA) with the dodecane radical cation (RH?+) has been measured by electron pulse radiolysis. Complexation of trivalent neodymium (Nd), gadolinium (Gd), and ytterbium (Yb) by TODGA yielded [Ln(TODGA)3(NO3)3] complexes that exhibited significantly increased reactivity (up to 9.3×) with the RH?+ radical cation, relative to the “free” ligand: k([Ln(TODGA)3(NO3)3] + RH?+) = (8.99 ± 0.93) × 1010, (2.88 ± 0.40) × 1010, and (1.53 ± 0.34) × 1010 M–1 s–1, for Nd(III), Gd(III), and Yb(III), respectively. The kinetic enhancement measured for both ligands exhibited a dependence on atomic number. Arrhenius parameters—specifically activation energies (Ea) and pre-exponential factors (A)—were determined for the reaction of “free” TODGA ligand with the RH?+ radical cation, giving: Ea(TODGA) = 17.43 ± 1.64 kJ mol–1, and A(TODGA) = (1.08 ± 0.02) × 1013 M–1 s–1. This draft manuscript has been prepared in fulfillment of Milestone M4FT-22IN030402024.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

A Revised International Standard for Gearboxes in Wind Turbine Systems

Gearbox and wind turbine design and application standards have contributed significantly to improvements in reliability over the past two decades. The International Electrotechnical Commission (IEC) 61400-4 standard of wind turbine gearbox design is currently being revised by a joint working group (JWG) of experts in IEC TC 88 (wind energy) and International Organization for Standardization (ISO) TC60 (gears) to further that effort. Experts from ISO TC4 (rolling bearings) and ISO TC28 (lubricants) have actively participated. This revision has implemented lessons learned from industry use of edition 1 since its publication in 2012. The main document, IEC 61400-4, was pared down to essential design requirements and application-specific recommendations along with a design verification framework. The JWG leveraged concurrent development of other standards, such as IEC 61400-8 on wind turbine structures, to replace edition 1 content. These are described along with how this works with the IEC Renewable Energy certification scheme for wind turbines (IECRE-WE). The JWG recognized the interest in maintaining informative parts of edition 1 including annexes on wind turbine architecture and loads, bearing and gear arrangements, bearing selection, lubrication system descriptions and lubricant performance recommendations. This information was retained in two technical reports: IEC/TR 61400-4-2 Lubrication and IEC/TR 61400-4-3 Explanatory Notes. Additionally, a technical specification, IEC/TS 61400-4-1, was drafted to provide a reliability calculation method for comparing different design options or conditions. Salient elements of these documents are described. All four documents were recently distributed for IEC/ISO review, ballot, and comment. Publication is expected in 2023.

gearbox↗

BOTTLE 1 - Introduction and BOTTLE Overview

The Bio-Optimized Technologies to keep Thermoplastics out of Landfills and the Environment (BOTTLE) Consortium aims to develop robust processes to upcycle existing waste plastics and to develop new plastics that are recyclable-by-design, both in direct alignment with DOE's Strategy for Plastics Innovation. We accomplish our work in the BOTTLE Consortium through an organizational framework that includes three primary research tasks, Deconstruction, Upcycling, and Redesign, which are supported by three cross-cutting tasks, Analysis, Characterization, and Modeling, BOTTLE also has tasks focused on Industry Engagement and Diversity, Equity, and Inclusion (DEI). This presentation will review the approach and management structure of BOTTLE, the importance of analysis-guided research, and the key metrics for carbon, economic, energy, and greenhouse gas emissions. In the FY21-FY23 period, BOTTLE has drafted and enacted a comprehensive DEI plan, assembled a world-class Technical Advisory Board (TAB) to provide constructive feedback on our performance, had our first in-person all-hands meeting in summer 2022, and on-boarded and off-boarded research activities based on active project management and analysis. From an impact perspective, BOTTLE researchers have published over 40 peer-reviewed manuscripts (many in leading journals), submitted >30 patent applications, and initiated 6 funds-in industry partnerships.

BIOMASS FUELS↗

A Revised International Standard for Gearboxes in Wind Turbine Systems: Preprint

Gearbox and wind turbine design and application standards have contributed significantly to improvements in reliability over the past two decades. The International Electrotechnical Commission (IEC) 61400-4 standard of wind turbine gearbox design is currently being revised by a joint working group (JWG) of experts in IEC TC 88 (wind energy) and International Organization for Standardization (ISO) TC60 (gears) to further that effort. Experts from ISO TC4 (rolling bearings) and ISO TC28 (lubricants) have actively participated. This revision has implemented lessons learned from industry use of edition 1 since its publication in 2012. The main document, IEC 61400-4, was pared down to essential design requirements and application-specific recommendations along with a design verification framework. The JWG leveraged concurrent development of other standards, such as IEC 61400-8 on wind turbine structures, to replace edition 1 content. These are described along with how this works with the IEC Renewable Energy certification scheme for wind turbines (IECRE-WE). The JWG recognized the interest in maintaining informative parts of edition 1 including annexes on wind turbine architecture and loads, bearing and gear arrangements, bearing selection, lubrication system descriptions and lubricant performance recommendations. This information was retained in two technical reports: IEC/TR 61400-4-2 Lubrication and IEC/TR 61400-4-3 Explanatory Notes. Additionally, a technical specification, IEC/TS 61400-4-1, was drafted to provide a reliability calculation method for comparing different design options or conditions. Salient elements of these documents are described. All four documents were recently distributed for IEC/ISO review, ballot, and comment. Publication is expected in 2023.

ENGINEERING,WIND ENERGY↗

Gas-Liquid Flow Modeling for Renewable Fuels Production

Aerobic/anaerobic and gas fermentation pathways have emerged as promising new technologies for the generation of renewable fuels/chemicals from biomass derived sugars, and mixtures of greenhouse/energy rich gas streams (CO2/CH4/H2/CO) via microbial action. Example pathways include sugars-to-ethanol conversion, biomethanation (CO2/H2 to CH4), biogas upgrading, CO fermentation and wet-waste conversion. Gas and liquid phase transport, mass-transfer, and mixing physics at large length scales can significantly affect microbial conversion rates, particularly when the microbial reaction requires a narrow set of conditions. These phenomena are difficult to study in small-scale bench-top reactors that are typically well-mixed. Predictive computational fluid dynamics (CFD) based simulations can therefore aid in the scale-up, design and optimization of these reactors. This work presents multiphase Euler-Euler CFD simulations of at-scale (~500 m3) bioreactors. Our mathematical model treats the gas and liquid as interpenetrating phases. This approach reduces the computational complexity of tracking individual gas bubbles that are several orders of magnitude smaller than reactor dimensions. We solve the Reynolds averaged Navier-Stokes (RANS) multiphase equations that account for phase and chemical species transport, interphase mass and momentum transfer and uses a phenomenological model for gas uptake by microbes. We use a customized solver derived from open-source CFD toolbox, OpenFOAM [1], to perform these simulations, which has been validated against small-scale reactors in our previous work [2]. There is currently a knowledge-gap regarding bubble-size distributions when using gas mixtures with vastly different properties, which can have a significant impact overall mass-transfer. For example, hydrogen bubbles are more buoyant compared to other relatively heavier gases (CO2/CH4/CO), resulting in a large distribution of residence times and bubble sizes. This work therefore develops a deeper understanding of bubble dynamics and interphase mass transfer in such heterogenous gas mixtures through well-resolved computational models. We use a population balance model (PBM) for bubble-size-distribution modeling that is validated against small-scale experiments in our solver with an uncertainty quantification study for bubble coalescence and break-up model parameters. Results pertaining to multiple simulations of gas-fermentation reactors are presented where gas mixtures with varying compositions of CO2/CH4/CO/H2 are imposed at the sparger boundaries. The spatio-temporal variations in bubble-size distribution and mass transfer coefficient are analyzed for varying superficial velocities and gas-compositions for varying sizes of bubble-column and airlift reactors. This work will also examine the performance of different reactor designs, viz. bubble column reactor, airlift reactor with an internal draft tube, and a stirred-tank reactor with Rushton impellers. Reactor mass-transfer coefficient, gas hold-up, and dissolved gas distribution are critically analyzed among reactors, and sensitivity studies pertaining to gas flow rates and reactor geometry will be presented. [1] Weller, H., Tabor, G., Jasak, H. and Fureby, C., A tensorial approach to computational continuum mechanics using object-oriented techniques, Computers in physics, 12, 6, 620--631, 1998. [2] Rahimi, M., Sitaraman, H., Humbird, D. and Stickel, J., Computational fluid dynamics study of full-scale aerobic bioreactors: Evaluation of gas-liquid mass transfer, oxygen uptake, and dynamic oxygen distribution, Chemical Engineering Research and Design, 139: 283-295.

BIOMASS FUELS↗

Environmental and Social Justice Implications of a Circular Plastics Economy

A consideration of environmental justice (EJ) and social justice (SJ) is critical to minimize the impacts of technology deployment on local communities. SJ and EJ impacts occur in specific geographic locations but can cover a wide range of effects (e.g., air pollution, access to clean water, jobs, wages, and education), making it challenging to determine which metrics are appropriate to evaluate and which data are required. Thus, there is currently a gap in the analysis community's ability to provide useful and universal EJ and SJ metrics for emerging technologies. Here, we present a draft framework for evaluating the human health, local environment, and job implications of processes that are at an early or middle technology readiness level (TRL). Using a case study on enzymatic polyethylene terephthalate (PET) recycling (middle TRL), we demonstrate how to qualitatively and quantitatively assess these EJ and SJ metrics for a circular economy context and how to communicate the results in a manner beneficial to both researchers and local communities.

circular economy↗

Establishment of technical basis to implement accident tolerant fuels and component to existing LWRs

Fuel cladding, channel box, and control rod designed with new materials and concepts have been developed in Japan for increasing accident tolerance of Light Water Reactors (LWRs). Fundamental data have been mainly accumulated from the viewpoint of material technology. In order to create the technical basis for the practical use of the accident tolerant fuels (ATFs) and the other components in LWRs, a program sponsored and organized by the Ministry of Economy, Trade and Industry (METI) of Japan has been initiated. Main candidate materials of the ATFs and components in Japan are silicon carbide (SiC), stainless steel including oxide-dispersion strengthened (ODS) FeCrAl alloys, and tri-structural-isotropic (TRISO) fuel. First of all, current status of development of the candidates was investigated using information released from inside and outside Japan. Based on the results of the investigation, technology readiness of the candidates was evaluated and the attribute guide was created to clarify technical subjects for the practical use as the core components of the existing LWRs. For that purpose, a technology readiness table was reviewed in terms of fuel rod design, production and quality management, core and plant design, safety evaluation for design basis accident and severe accident, safety evaluation for transport and storage, establishment of treatment and disposal technologies, and development of standards and criteria, with 9 readiness levels. Considering the reviewed technology readiness table and the additionally evaluated influence of implementation of the new materials, a map of remaining subjects for research/development (Attribute guide) was prepared. Finally, a research plan was drafted for design and fabrication towards implementation of ATFs and components to the existing LWRs. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Breakaway oxidation of ZIRLO and optimized ZIRLO cladding per 10CFR50.46c criteria

The United States Nuclear Regulatory Commission (NRC) in 10CFR50.46c proposed changes to the loss of coolant accident (LOCA) criteria for LWR licensees including a new requirement to test cladding materials for breakaway oxidation. Cladding materials must be shown to resist breakaway oxidation long enough for the LOCA transient to be terminated. The onset of breakaway oxidation is characterized by a rapidly increasing rate of oxidation and the absorption of hydrogen resulting in a loss of cladding integrity. The proposed rule changes effectively require some manner of periodic and on-going testing to monitor the population of cladding for breakaway resistance. More than 200 lots of production cladding material have been tested in accordance with the draft regulatory guidelines. Testing has been conducted in a steam environment at the critical temperature for breakaway oxidation for durations that exceed the analytical endurance limit required to comply with the breakaway oxidation test criteria. The alloys that have been tested include both ZIRLO cladding and Optimized ZIRLO cladding. Breakaway oxidation testing consisted of three basic steps: preparation of test specimens, high temperature steam oxidation and post-test specimen evaluation. The results show there is a high probability that all ZIRLO and Optimized ZIRLO lots will pass production certification testing. Variations in response to breakaway oxidation testing were observed only in testing that ran well beyond the maximum LOCA duration of 2000 seconds. No indications of early breakaway oxidation were observed in the testing of production material that has been completed thus far. This provides confidence that a sampling approach to breakaway oxidation testing and monitoring remains a sound approach.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Decontamination and Decommissioning Program of a Radiopharmaceuticals Production Facility - 17103

On May 2012, Best Medical Belgium (BMB) S.A., a manufacturer of pharmaceutical products located on the nuclear site of Fleurus, was declared bankrupt. According to the Belgian law, ONDRAF/NIRAS (Belgian Radioactive Waste Management Agency) was entrusted with the clean-up and the decommissioning operations of the former BMB facilities, nowadays known as 'ONDRAF/NIRAS Site Fleurus' (ONSF). In June 2015, ONSF launched a Decontamination and Decommissioning (D and D) program, for which Tractebel supports the definition of the clean-up and decommissioning strategies; the drafting of the Final Decommissioning Plan (FDP) and License Application for decommissioning; and the follow-up of the clean-up and upcoming D and D works on site. Four nuclear buildings are part of the clean-up and D and D activities. One of them, Building 14 (B14), represents the most challenging task with the clean-up of highly contaminated areas and their further decommissioning up to greenfield. Beside its two cyclotrons successively used for the production of radioisotopes, this building features hot cells and glove boxes used for the purification of radioisotopes and the conditioning of the final pharmaceutical product. The present paper aims at presenting the development of the D and D program in terms of modifications of existing facilities to allow carrying out the clean-up and D and D activities and the management of dismantled radioactive materials in a safe, efficient and cost-effective way as well as in terms of strategic options to be developed for the FDP. To support the clean-up and D and D activities, several workshops have been designed in order to treat radioactive materials removed from the building rooms. Those workshops feature an input buffer storage area, a common output buffer storage area and installations for the treatment of radioactive materials and waste (handling devices, cutting means, decontamination means, free release measurements means, etc.). Some modifications to the existing auxiliary systems will be required in order to dispose of appropriate systems to operate those workshops in a safe way. Activated concrete structures will constitute the most important part of radioactive materials that will arise from the decommissioning activities. To limit the total decommissioning costs, and especially the costs associated to radioactive waste management, two strategies have been developed in order to manage a part of activated concrete as candidate for free release with a certain decay period or as candidate for conventional landfill. Both strategies will have to be further detailed and discussed with the competent Authorities to ensure they can actually be implemented. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

In Situ Disposal to Optimize Decommissioning Waste Management - 17455

Cavendish Fluor Partnership (CFP) is teaming with the UK government's Nuclear Decommissioning Authority (NDA) to explore opportunities for onsite disposal of structures and wastes from decommissioning of twelve Magnox nuclear sites. CFP is piloting implementation of draft guidance issued by the Environmental Agency (EA), Scottish Environmental Protection Agency (SEPA) and Natural Resources Wales (NRW) designed to optimise management of wastes generated in closing nuclear sites positioned across Scotland, Wales and England. Where it can be demonstrated to be the best overall solution for people and the environment, on-site / in situ disposal as an option for optimising waste management could save millions of pounds sterling in the overall costs for site closure as opposed to previous plans that required retrieval, packaging, transportation and offsite disposal of all radioactive wastes generated during site decommissioning. The UK government's Department for Business, Energy and Industrial Strategy (BEIS), NDA, and UK regulators are consulting with stakeholders on a proposal to amend legislation and enable better, more proportionate regulation of nuclear sites in the final stages of decommissioning and clean-up. Practical application of existing UK legislation typically means removing most, if not all, radioactive waste and residual contamination from the nuclear licensed site for disposal or management elsewhere, irrespective of any wider health and safety, social, environmental or economic considerations. Proposed changes to legislation would give greater weight to the environment agencies' guidance and provide for a more sustainable approach where optimization could include on-site/in situ disposal solutions and early opportunities to reuse land with appropriate regulatory oversight. Recent characterization activities at two reactor sites have identified areas of sub-grade low level contamination in structures and soil around used fuel ponds. CFP, a partnership of UK-based Cavendish Nuclear Limited and US-based Fluor Corporation, has initiated preliminary site modelling that indicates much of this material, including significant volumes of sub-grade structures would be conducive for in situ disposal under the new proposed guidance. Based on Fluor experience with similar decommissioning projects at US Department of Energy sites, CFP will look to leverage in situ disposal to optimise decommissioning waste management and consequently optimise overall facility decommissioning strategies. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗