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Article drafted to be submitted to Elsevier publishing to determine interest. The draft will change depending on peer review and acceptance comments.
Microreactors are advanced reactors that are designed to be small, scalable, and portable with up to 20 MW power. These reactors could operate independently, or as part of a microgrid, without need of a frequent refueling. Micro-reactors are designed to be deployable to provide electric power in remote locations, therefore providing greater flexibility. Several micro-reactors are under development in the US. These reactors are based on advanced gas-cooled or heat-pipe concepts. While Graphite can be found in various applications, some high-temperature reactors plan to employ Graphite in their core components due to its role as a moderator and its ability to maintain its structural integrity when subjected to elevated temperatures and high neutron fluence. Although there is significant experience with use of Graphite in nuclear applications, there are still unknowns that should be addressed. Graphite properties depend on the graphite type and affected by the fabrication procedures. Material properties are functions of the temperature and irradiation dose. The fundamental properties also affected by the oxidation environment. Therefore, in-depth understanding of graphite properties, including the effect of irradiation, oxidation and other influencing parameters are required to evaluate the design accurately. This draft aims to provide a comprehensive review of material properties for Graphite relevant to micro reactor design. For this work, two distinct grades of graphite were considered, namely IG-110 and Mersen-2114. Physical, thermal, and mechanical properties for these grades were comparatively evaluated. The properties that are discussed in this draft aim to serve as a basis for design and safety analysis.
U.S. Nuclear Regulatory Commission (NRC) is currently assessing ASME Section III, Division 5 (2017 Edition) and accompanying Code Cases for endorsement Draft Regulatory Guide (DG-1380) and draft NUREG (2245) on the endorsement of Division 5 were issued and public comment phase completed DG-1380 places conditions in the areas of general requirements, mechanical design, metallic materials allowable stresses, and graphite materials/design of Division 5 DG-1380 is a revision to Regulatory Guide 1.87, Revision 1, 1975 (which endorsed the 159X series of ASME Code Cases, with conditions) NRC staff is currently reviewing the low-temperature and elevated temperature Alloy 617 code cases for endorsement Results of the review will be incorporated into DG-1380 and changes will be announced publicly The formal endorsement of Section III, Division 5 and accompanying code cases, with conditions, will be made through Regulatory Guide 1.87, Revision 2
The High Burnup Spent Fuel Data Project (herein referred to as the 'project'), sponsored by the US Department of Energy (DOE) Office of Nuclear Energy (NE), is focused on experimentally defining the effects of long-term storage and transportation on high burnup (HBU) pressurized water reactor (PWR) fuel (>45 gigawatt days per metric ton uranium). The goals of the project are to provide confirmatory data for model validation and potential improvement; to provide input to future dry storage cask design; to support license renewals and new licenses for Independent Spent Fuel Storage Installation facilities; and to support transportation licensing for high burnup used fuel. In support of these project goals, an instrumented TN-32B bolted-lid cask at the North Anna reactor site will be loaded with intact, HBU PWR fuel assemblies (project assemblies) having four different kinds of cladding: standard Zircaloy-4, low-tin Zircaloy-4, ZIRLO, and M5. In approximately 10 years, the instrumented cask will be opened for inspection and several fuel rods from the project assemblies will be characterized. To support the project goals, the project pulled 25 'sister rods', 9 from the project assemblies and 16 from similar HBU assemblies, for characterization. The 25 sister rods are all high burnup and cover the range of cladding alloys. The 25 sister rods were shipped to Oak Ridge National Laboratory (ORNL) in early 2016 for detailed nondestructive and destructive examination. Examinations are intended to provide baseline data on the initial physical state of the cladding and fuel prior to the loading, drying, and long-term dry storage process. Further examinations are focused on determining the effects of temperatures encountered during and following drying. Similar tests will be performed on rods taken from the project assemblies at the end of the storage period (the 'cask rods') to identify any significant changes in the fuel rods that may have occurred during the dry storage period. Additionally, some of the sister rods will be used for separate effects testing to expand the applicability of the project data to the fleet, and to address some of the data-related gaps associated with extended storage and subsequent transportation of high burnup fuel. A draft test plan is being developed that describes the experimental work to be conducted on the sister rods. This paper summarizes the draft test plan and necessary coordination activities for the multi-year experimental program to supply data relevant to the assessment of the safety of long-term storage followed by transportation of high burnup used fuel. (authors)
Radioactive waste resulted in the past in Iraq from a number of nuclear activities and facilities all of them seriously damaged or destroyed during the Gulf war. The task of decommissioning such facilities and managing the resulting waste is being supported by the International Atomic Energy Agency (IAEA), the European Union (EU), and the United States (US). A national policy for radioactive waste management for Iraq has been drafted by the Ministry of Science and Technology (MoST); a draft strategy for radioactive waste management implementation is in preparation. In this framework, Iraq is considering locating a radioactive waste disposal facility at the Al-Tuwaitha site, near the capital city of Bagdad. In the framework of its Instrument for Nuclear Safety Cooperation the EU has recently started a cooperation project named 'Feasibility Study, Basic Design, and Engineering Design of an Engineered Radioactive Waste Disposal Facility' for Iraq (Project IQ4.01/11). The project aims at producing the design of a repository for the radioactive waste resulting from the decommissioning activities and from the continuing use of radioisotopes in medicine and the oil and gas industry in the country. The contract for this cooperation project was awarded by the European Commission in April 2015 to the consortium of two international engineering companies, Nukem Technologies Engineering Services GmbH and DBE Technology GmbH, both of Germany, and Javys a.s., the national waste management agency of Slovakia. The planned Iraqi near-surface repository is constrained by the complex security conditions in the country. This has led to the decision of using whenever possible the Al-Tuwaitha site, were most of the waste is located, as the repository location. The project work will therefore focus on assessing whether and which part of the waste expected to result from the decommissioning and remediation activities is amenable for surface disposal in an appropriately engineered facility. In addition, careful review of the site characteristics shall provide enough elements to justify and validate the political decision of disposing of the waste in Al Tuwaitha. Thereafter, the project work will focus on the conceptual and later the engineering design of the repository. Finally, a Safety Analysis will provide the basis for regulatory decisions about the further steps for realization of the Iraqi final disposal facility. (authors)
On May 2012, Best Medical Belgium S.A. (BMB), 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 decommissioning operations of the former BMB facilities, nowadays known as 'ONDRAF 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; - Drafts the Final Decommissioning Plan (FDP) and Safety Analysis Report (SAR) that will be submitted to FANC/AFCN (Belgian Federal Agency for Nuclear Control) in order to get the License for decommissioning; - Drafts the technical specifications of the public tendering process related to the D and D program; - Ensures the day to-day follow-up of the D and D activities on site. Four nuclear buildings are part of the D and D activities. One of them, building 14 (B14), represents the most challenging and extensive task with the clean-up of highly contaminated areas and its further decommissioning up to the final state. This building features two cyclotrons (CGR and IBA cyclotrons) successively used to produce radioisotopes, as well as hot cells and glove boxes used for their purification and the conditioning of the final pharmaceutical product. The present paper aims at presenting the most recent development steps of the clean-up phase regarding the adaptations of existing facilities and the upcoming activities in preparation of the decommissioning activities. To allow the sorting and the treatment of the radioactive material identified in the physical and radiological inventory, several workshops have been implemented within the B14 building in order to deal with radioactive materials arising from the clean-up and D and D activities. Following the conceptual design phase, Tractebel has actively monitored the on-site activities for the construction of those workshops such as: - The modification of the civil works; - The revamping of the ventilation system; - The installation of dedicated lifting equipment and workstations equipped with cutting devices; - The assembly of a docking station for filling the radioactive packages. The removal of the activated concrete surrounding the IBA cyclotron requires the erection of a containment structure and an extension structure. The containment structure, composed of light metallic beams, is located above the cyclotron and its irradiation zones. For operational security reasons and working efficiency, the cutting process of the concrete ceilings and walls will be performed from the top inside the containment structure by means of an eight tons overhead bridge crane. Concrete blocks resulting from the cutting process will then be lifted, without any loss of containment, towards the extension zone of the nuclear zone of the IBA cyclotron for further resizing, sorting and evacuation towards the identified waste routes. To prepare this task which will be performed during the decommissioning phase, Tractebel sets up the necessary technical specifications. (authors)
During WM2018, the work being done under the International Atomic Energy Agency (IAEA)'s Modelling and Data for Radiological Impact Assessments (MODARIA) II Programme (https://wwwns.iaea.org/projects/modaria/modaria2.asp?s=8 and l=129) was introduced. The Programme comprises seven working groups covering a wide range of topics. Amongst them, Working Group 1 (WG1) is focused on dose assessment and decision aiding tools to address existing exposure situations due to past practices involving naturally occurring radioactive material (NORM) and nuclear legacy sites. Specifically, this covers the development of methods and toolsets for risk-informed decision-making for such complex sites, and includes practical demonstration of decision-making processes and tools through case studies. During 2018 WG1 participants met twice to discuss the status and plans of work being conducted by the WG. The group held its Second Interim Meeting from 7 to 11 May 2018 at the Jozef Stefan Institute (JSI) in Ljubljana, Slovenia. The objectives of the meeting were to: (1) Discuss the status of WG1 work; (2) Start preparation of the interim draft version of the MODARIA II WG1 Report (herein referred to as the 'Interim Report'); (3) Review the progress of planned data analyses, model-model comparisons, and model-data comparisons being conducted through case studies for the Tessenderlo Chemie Site in Belgium, the Zapadnoe Uranium Mill Tailings Site in Ukraine, and a Former Tin Processing Facility Site in Brazil; (4) Discuss calculations conducted for a NORM Site in China for potential addition to the WG1 case studies; (5) Report on progress on topical studies and other assignments performed to support the preparation of several sections of the Interim Report; and (6) Discuss plans for incorporating some preliminary case studies considered by MODARIA I WG1 and MODARIA I WG3. During the meeting in Slovenia, WG1 participants also visited the Zirovski vrh (RZV) Uranium Mine and Mill Tailings Site near Ljubljana. From 22 to 25 October 2018, WG1 members also participated in the MODARIA II Third Technical Meeting in Vienna, Austria. The meeting facilitated analysis of the progress made so far by the seven working groups, as well as exploration of the dissemination of the results of the MODARIA II Programme through publication in scientific journals dealing with the various subject areas covered by the Programme. WG1 participants focused on the preparation of its Interim Report, and engaged in technical exchanges with the IAEA Le Trench Project on characterization, assessment, remediation and management of buried waste at legacy trench sites, as well as the To Enhance uncertainties Reduction and stakeholders Involvement Towards integrated and graded Risk management of humans and wildlife In long-lasting radiological Exposure Situations (TERRITORIES) project (https://territories.eu/). Currently, WG1 is in the process of preparing a draft report to document the results of its various case studies and special topics, and is preparing for the final Interim Meeting in May 2019 and the final Technical Meeting in October 2019, before the conclusion of the MODARIA II Program at the end of 2019. This paper will provide a status update of these activities, along with preliminary information on the WG1 report, including potential recommendations for future activities. (authors)
DOE Order 458.1, Radiation Protection of the Public and Environment, was issued in 2011. DOE sites were given 18 months to implement. The revised Order promulgates requirements for property clearance actions and independent verification. DOE Order 458.1 allows for preapproved authorized limits for the clearance of property. However, when property with the potential to contain residual radioactive material does not meet preapproved authorized limits, an authorized limits package must be developed. The Order contains a range of requirements for demonstrating with reasonable assurance that dose constraints are met for any actual or likely future use of the property to be released. EM has developed a draft guidance document that provides the elements of an authorized limits package. These elements are used to review all authorized limits packages that are submitted to EM. Expected elements include property description and process knowledge documentation, current and likely future use, the conceptual site model, dose modeling methodologies, specific authorized limits, dose- or concentration-based constraints, collective dose estimate to the potentially exposed population, stakeholder communications, description of the As Low As Reasonably Achievable (ALARA) analysis, implementation plan, evaluation of difficult to assess surfaces, and independent verification plan. The draft guidance document also provides further explanation of the desired elements of an independent verification (IV) plan. An IV plan should describe the planning phase, implementation phase, assessment phase, and decision phase of an activity. The planning phase includes scope and cost, concurrent with cleanup contractor procurement, and review and approval of site radiological survey clearance program and IV program plans. The implementation phase assures sufficient collection of data and adjustment can be made as necessary. During the assessment phase, data and reports are reviewed, and coordination between the clean-up contractor and IV personnel occurs. A decision of whether or not the clearance actions need to be altered occurs during the decision phase. IV certification that the clearance action is complete also occurs during the decision phase. Issuance of the final guidance document is meant to improve the consultation process and minimize iterative interactions with EM. Standardizing and formalizing property clearance and IV actions also helps assure that cleanup actions are transparent and sustainable for future scrutiny. (authors)
The final draft of a revision to IEEE Std. 1012-2012, 'IEEE Standard for System, Software and Hardware Verification and Validation', is expected to be approved for publication in June 2017. A draft of NEI 96-07, Appendix D, 'Supplemental Guidance for Application of 10 CFR 50.59 to Digital Modifications', has been submitted to the NRC staff for review and endorsement. What, if any, relationship exists between these two documents? How can the nuclear industry utilize the first one to help ensure success when applying the second one? NRC Regulatory Guides only endorse digital system and software related industry standards for application to safety-related systems and components, but the vast majority of digital modifications are made to non-safety related systems and components, so are these industry standards of little or no use when performing digital upgrades to non-safety related equipment? This paper answers these and other related questions and shows how application of a graded approach to verification and validation, utilizing the IEEE Std. 1012 concept of 'integrity level', can increase the likelihood of a 10 CFR 50.59 evaluation outcome that does not require prior NRC review and approval for non-safety related digital modifications. (authors)
The Organisation for Economic Co-operation and Development (OECD), the Nuclear Energy Agency (NEA), the International Reactor Physics Experiment Evaluation Project (IRPhEP) continue to preserve and evaluate integral reactor physics experiment data to support nuclear energy and technology needs. International contributions are collated within the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook). The 2021 edition of the IRPhEP Handbook now contains data for 57 unique nuclear facilities with benchmark specifications for 169 experimental series, of which four are draft evaluations. Distributed with the IRPhEP Handbook and available online is the IRPhEP Database and Analysis Tool (IDAT), allowing users to search and interrogate the data. Since Physor 2018, there have been 11 minor revisions to existing benchmark evaluations, significant revisions to two evaluations, one draft evaluation, and nine new evaluations. The corona virus pandemic has delayed international activities supporting the production of additional content for the IRPhEP Handbook. However, efforts continue for numerous endeavors to complete new reactor physics benchmark evaluations to support current and future validation needs. Those interested in serving as evaluators and/or reviewers are strongly encouraged to participate. This paper provides a summary of IRPhEP content and activities since Physor 2018. (authors)
I am defending my PhD thesis soon at Georgia Institute of Technology. The work contained in Chapter 4, sections 1 through 5, has been done with Sandia during my internship, while everything else has been done independently and through the NDSEG fellowship program while at Georgia Tech. This approval is needed to send the draft to my committee as soon as possible before an August 5th defense date, with the goal of publishing the finished draft by August 23rd.
Strain 11 T was isolated from water of an artificial lake accumulating industrial wastewater on the outskirts of Celje, Slovenia. In this paper, phenotypic characterisation showed strain 11 T to be a Gram-stain positive, spore forming bacterium. The 16S rRNA gene sequence identified strain 11 T as a member of the genus Paenibacillus, closely related to Paenibacillus alvei (96.2%). Genomic similarity with P. alvei 29 T was 73.1% (gANI), 70.2% (ANIb), 86.7% (ANIm) and 21.7 ± 2.3% (GGDC). The DNA G+C content of strain 11 T was determined to be 47.5%. The predominant menaquinone of strain 11 T was identified as MK-7 and the major fatty acid as anteiso-C 15:0 . The peptidoglycan was found to contain meso-diaminopimelic acid. In contrast to its close relatives P. alvei DSM 29 T , Paenibacillus apiarius DSM 5581 T and Paenibacillus profundus NRIC 0885 T , strain 11 T was found to be able to ferment d-fructose, d-mannose and d-xylose. A draft genome of strain 11 T contains a cluster of genes associated with type IV pilin synthesis usually found in clostridia, and only sporadically in other Gram-positive bacteria. Finally, genotypic, chemotaxonomic, physiological and biochemical characteristics of strain 11 T presented in this study support the creation of a novel species within the genus Paenibacillus, for which the name Paenibacillus aquistagni sp. nov. is proposed, with strain 11 T (=ZIM B1027 T =LMG 29561 T =CCM 8679 T ) as the type strain.
The Barents Sea is one of the fastest changing regions of the Arctic, and has experienced the strongest decline in winter-time sea-ice area in the Arctic, at 22364% decade21. Sea-ice thickness in the Barents Sea is not well studied. We present two previously unpublished helicopter-borne electromagnetic(HEM) ice thickness measurements from the northwestern Barents Sea acquired in March 2003 and 2014.The HEM data are compared to ice thickness calculated from ice draft measured by ULS deployed between1994 and 1996. These data show that ice thickness varies greatly from year to year; influenced by the thermodynamic and dynamic processes that govern local formation vs long-range advection. In a year with a large inflow of sea-ice from the Arctic Basin, the Barents Sea ice cover is dominated by thick multiyear ice;as was the case in 2003 and 1995. In a year with an ice cover that was mainly grown in situ, the ice will be thin and mechanically unstable; as was the case in 2014. The HEM data allow us to explore the spatial and temporal variability in ice thickness. In 2003 the dominant ice class was more than 2 years old; and modal sea-ice thickness varied regionally from 0.6 to 1.4 m, with the thinner ice being either irst-year ice, or multiyear ice which had come into contact with warm Atlantic water. In 2014 the ice cover was predominantly locally grown ice less than 1 month old (regional modes of 0.5–0.8 m). These two situations represent two extremes of a range of possible ice thickness distributions that can present very different conditions for shipping traffic; or have a different impact on heat transport from ocean to atmosphere.
The immersed moving boundary (IMB) scheme has been extensively used to couple the discrete element method (DEM) with the lattice Boltzmann method (LBM). In the literature, only the formulation of IMB for lattice nodal cells covered by a single-solid particle was given. The treatment of situations where a nodal cell is covered by two or more solid particles is seldom discussed. It is found that some numerical instability can occur for such situations due to an inappropriate computation of the weighting function in the IMB formulation. This work presents an enhanced treatment that can resolve the issue and validates it using some benchmark tests. Furthermore, to avoid the extra costs associated with the treatment and simplify the complicated procedure introduced, a simplified IMB scheme is proposed. The accuracy of both enhanced and simplified IMB schemes are validated by test cases including single-particle sedimentation, two-particle drafting-kissing-tumbling phenomenon, and multiple-particle sedimentation. Then, the robustness of both schemes is examined and discussed using a specially designed flow past cylinders test. Overall, the simplified IMB scheme is proved to be robust and sufficiently accurate and simpler and more effective than the enhanced scheme.
To achieve useful, fair, and cost-effective design qualification and type approval testing for PV inverters, two procedures were developed and demonstrated to evaluate the bus link capacitors and power transistor—and where applicable, its module—for long-term reliability. We evaluate the inverter under simulated use conditions with heat run tests to find the highest operating temperatures reached by these components. The procedures are demonstrated in this study with a 4-kVA class string inverter. The maximum temperature of the DC bus link capacitors was determined to be 76.4°C when the ambient temperature was at the inverter's maximum rated temperature of 60°C with derating occurring. On the other hand, the power transistor module's maximum temperature using the heat sink temperature as the index, 92.6°C, occurred in an ambient of 40.8°C when derating was not occurring. The conditions found for upper temperatures exhibited by these components are, respectively, proposed for implementation in the dry heat and thermal cycling tests in the IEC 62093 “Power conversion equipment for photovoltaic systems – Design qualification testing” international standard draft so that the levels applied in the tests are in proportion to those experienced in the field. Finally as a result, fairer evaluation of inverter reliability is realized.
Aureobasidium pullulans is a yeast-like fungus with remarkable phenotypic plasticity widely studied for its importance for the pharmaceutical and food industries. So far, genomic studies with strains from all over the world suggest they constitute a genetically unstructured population, with no association by habitat. However, the mechanisms by which this genome supports so many phenotypic permutations are still poorly understood. Recent works have shown the importance of sequencing yeast genomes from extreme environments to increase the repertoire of phenotypic diversity of unconventional yeasts. In this study, we present the genomic draft of A. pullulans strain from a Patagonian yeast diversity hotspot, re-evaluate its taxonomic classification based on taxogenomic approaches, and annotate its genome with high-depth transcriptomic data. Here, our analysis suggests this isolate could be considered a novel variant at an early stage of the speciation process. The discovery of divergent strains in a genomically homogeneous group, such as A. pullulans, can be valuable in understanding the evolution of the species. The identification and characterization of new variants will not only allow finding unique traits of biotechnological importance, but also optimize the choice of strains whose phenotypes will be characterized, providing new elements to explore questions about plasticity and adaptation.
Molten metal atomization in close-coupled gas atomization dies can operate between two limiting conditions, jetting and filming, together with several complex mechanisms: liquid-gas drafting, downward/upward shearing, melt bouncing, etc. Liquid jet deformation depends on flow and geometric parameters, such as liquid Reynolds, liquid Weber, and gas Mach numbers, as well as gas jet apex angle and melt tube tip extension and aspect ratio, among others. Understanding their effect is of importance for the metal powder making industry. Numerical gas atomization studies can provide approximated flow information and consider a wide range of conditions, beyond experimental reach. Here, 3D high-resolution simulations employing a 5-equation compressible flow model coupled with the volume-of-fluid method are compared with experiments, for liquid Weber number in the range of 1–30 and liquid Reynolds number below 10,000. This validation explores the predicting capabilities of the numerical model.
Although Tribal land represents more than 5% of the solar photovoltaic technical potential in the United States, this resource is largely untapped due to a range of barriers, including complex project economics, Tribal technical and human resource capacity, project funding and financing obstacles, and regulatory challenges. To identify and better understand the regulatory barriers, the National Renewable Energy Laboratory (NREL) and the Midwest Tribal Energy Resources Association (MTERA) engaged Tribes, utilities, and regulators. Funded by the U.S. Department of Energy, the 3-year effort seeks to address regulatory challenges or barriers that affect Tribal solar projects differently - specifically or disproportionately because they are located on Tribal lands. This paper, largely excerpted from a comprehensive (draft) guidebook released by NREL and MTERA, provides an overview of 13 key regulatory barriers identified through this research, as well as potential short- and long-term solutions. In addition, the paper points to potential pathways for addressing key barriers through case studies highlighting successful Tribal solar projects along with considerations for stakeholders working with Tribes. These resources can support stakeholders in creating meaningful relationships and pursuing workable solar projects.