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

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At least 1,081 records · Page 60

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

FeCrAl alloys are promising candidate materials for the accident tolerant fuel (ATF) cladding application due to their exceptional resistance to oxidation in elevated temperature steam environments. Currently, limited fracture toughness data are available for the FeCrAl alloys, including the FeCrAl alloys newly developed at Oak Ridge National Laboratory (ORNL) under the U.S. Department of Energy’s Advanced Fuels Campaign (AFC) program. In this study, two Generation II candidate FeCrAl alloys, i.e., C06M (81.8Fe-10Cr-6Al-0.03Y-2Mo-0.2Si) and C36M (78.8Fe-13Cr-6Al-0.03Y-2Mo-0.2Si), were irradiated in the High Flux Isotope Reactor (HFIR) at ORNL to assess the fracture characteristics of these alloys after neutron irradiation. A total of six rabbit capsules were irradiated in HFIR at target temperatures of 200°C, 330°C, and 500°C up to target damage doses of 8 displacements per atom (dpa) and 16 dpa. Post-irradiation fracture toughness testing was performed following the Master Curve method in the ASTM E1921 standard. The main findings of this study are:1) Both the C06M and C36M alloys exhibited a similar response to irradiation concerning irradiation hardening and embrittlement.2) The irradiation temperature played different roles in terms of irradiation hardening and embrittlement for both C06M and C36M: after irradiation between 166°C and 204°C, both materials exhibited significant irradiation hardening and embrittlement; after irradiation between 315°C and 343°C, both materials showed small irradiation hardening without irradiation embrittlement. After irradiation between 501°C and 507°C, however, the irradiation softening without irradiation embrittlement was observed in both materials.3) Comparing the microhardness and Master Curve reference temperature T0q before and after neutron irradiation, we did not observe a linear correlation between the two parameters for both C06M and C36M steels. This should be mainly due to a flat response of the Master Curve reference temperature T0q to the irradiations at 166–204°C and 315–343°C ranges4) C06M showed a lower T0q, meaning better toughness, than C36M at the unirradiated condition, and such trend was kept even after neutron irradiation except for the 166–204°C irradiation after which both materials had similar T0q.5) In terms of hardening and embrittlement, the irradiation effect on both C06M and C36M appeared to saturate after an irradiation dose of 7 dpa.

Chen, Xiang↗

Right-Sized Reuse - Use a Systematic Process, and Design for a Specialized, Yet Flexible Result - 13558

The process of transferring real property from the U.S. Department of Energy (DOE) is always the same - except when it's not. The most frequently asked questions in the process are: how can this take so long and be so complex, and why is it different every time? The process of transferring real property from the Department of Energy is always the same - except when it's not. Repeat as needed. The authority for DOE to transfer property is found in the Atomic Energy Act of 1954 (AEA). Specifically, the transfer of real property for mission-related purposes is done pursuant to the AEA Section 161(g). Another rule that can provide certain unique benefits to the transferee is found in 10 Code of Federal Regulations (CFR) Part 770, Transfer of Real Property at Defense Nuclear Facilities for Economic Development; it can be followed for economic development purposes at defense nuclear facilities. All federal real property transfers include at minimum a National Environmental Policy Act (NEPA) review and a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) chap. 120(h) environmental due diligence evaluation. The end-point objective is to be able to demonstrate that a transfer is protective of human health and the environment - typically attained via a risk evaluation. That's it...mostly. None of these requirements are new; their processes are well-known. So, why is it different every time there is a transfer and what can be done to move things along? Time and the perception of open-ended schedules kill projects. Economic development projects that are proposed by Community Reuse Organizations (CROs) and others or by parties who need private capital are especially time-sensitive. It is not reasonable to expect business interests or investors to wait two years while the property transfer process is carried out. Lenders are also risk-sensitive and not solely business-risk sensitive. After all, these are federal properties where contamination is a factor. What are some of the things you can do to address those time and risk issues? Issues of time and complexity arise from several variables. Short-sighted vision and lack of project definition lead to wasted effort and lengthy delays. Some variability on the input side of the process can be controlled in a way that will save you time and actually work to your advantage. Steps can be taken to systematize the transfer process on the agency's part and on the requester/grantee's part. Having the right mix of dedicated people from the beginning, planning with flexibility, coordinating with the clean-up program at your site, knowing the interests and issues of your stakeholders, and working with the CRO/economic development authorities - all of these measures and others can and will help you. The key is not simply knowing the steps and making a punch-list, but understanding the steps and how to work with and use them. These concepts can be applied to create a vision of success for those engaged in real property transfer. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Success in commissioning a key U.S. radioactive waste burial site through the technical support of Dufrane Nuclear Shielding Incorporated (DNSI) - 15476

With the -phase out- of the South Carolina based Barnwell Radioactive Waste Burial Site, and the stockpile and storage of radioactive waste and irradiated components throughout the U.S. Nuclear Industry for decades, the opening of the Texas Low-Level Radioactive Waste Disposal Compact Facility by Waste Control Specialists (WCS), is a game changer in solving this industry-wide issue. For the first time in decades, generators now have the opportunity to send their waste to a site specifically designed to permanently sequester the waste in a licensed facility that will protect public health and the environment, better than any built to date. As history has shown through the many decades of the U.S. Commercial and Federal Nuclear Industry, site operators and management have relied heavily on contractors and vendors with exceptional expertise and decades of experience to achieve success and meet their goals. The commissioning of WCS was no exception as DNSI was contracted to design, develop, build and deploy a major component required for the opening and successful operation of the WCS site. This component, being the Modular Concrete Canister (MCC), is the -work horse- of the site. With its enormous size, weight and strength, it provides many functions that meet and comply with the site performance assessment (PA) under 10 CFR Part 61, the site WAC, and Texas Low-Level Radioactive Waste Disposal Authority. Offsite contracting the production and delivery of this critical component was a major step toward success in meeting schedule and cost for the much needed opening of the Texas Compact and Federal site. In selecting a shielding vendor, WCS partnered with a U.S. Nuclear Service company with over 30 years of experience which spans the entire U.S. Commercial, Federal, and Nuclear Industry. The task given DNSI was not a simple one, it involved every aspect from start to finish of the design, production and delivery of rectangular, cylindrical and -irradiated hardware- (IH) MCCs, that could accept waste up to 100 Sv /Hr contact dose rates. The enormity of this project was quite clear and required extensive quality control, construction of batch plants, purchase of huge quantities of raw materials, setting up a production site in a neighboring city, relocation of personnel from company headquarters, and safely transporting 8,000 Tons of MCC components 75 miles one-way on West Texas highways daily. Most important of all, this was accomplished safely with no incidents, no component failures or rejects, and on schedule. The start of receipt, of -in-compact waste- and -out-of-compact waste- was conducted virtually in a 3 month period time span. To help guarantee success and quality of product, all forms had surfaces machined, heavy duty elastomer coatings were applied to concrete surfaces, only galvanized anchors were used, and the batch plant was run to strict ASME standards thus testing every 50 cubic yards of concrete poured. With significant teamwork and success from Vendors such as DNSI, WCS and the Texas Compact has evolved as one of the leading radioactive waste sites in the U.S. and the world, providing safe, secure and compliant permanent waste disposal services by using technical expertise and innovation of the highest standards. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Software Dependability for Digital Instrumentation and Control Systems in Nuclear Power Plants - Lessons Learnt from a DOE Sponsored Project

This paper discusses the lessons learnt from a sponsored study undertaken under the sponsorship of the Department of Energy by a team of scientists at the Ohio State University in collaboration with Technology Resources and experts around the world. This paper makes recommendations for future research and studies based on these lessons learnt. The purpose of the research was to provide a software dependability quantification framework that would allow its evaluation along the software development life cycle for safety critical instrumentation and control systems (I and C) such as those found in nuclear power plants. A typical example of safety critical system is the reactor protection system. The research funded by the Department of Energy built on preliminary research carried out for the US NRC that had focused solely on software reliability quantification. Quantification of software dependability is important for safety critical I and C because the regulatory framework in use in the United States for nuclear power plants is risk informed. Quantification of risk requires quantification of all contributors to risk and those include instrumentation and control systems. The purpose of the study was to help developers of software-based I and C with an early evaluation of the potential risk an application would represent at different stages of the software development life cycle by building gates at the end of each life cycle phase. Life cycle phases of software development comprehend phases such as requirements, design, coding and test. The gates' function would be to stop development from moving forward if the assessed dependability objective for that phase were not met. Gates thresholds were to be defined based on measurements collected during the life cycle phase under evaluation and phases that preceded it and an understanding of the mechanisms that would lead to threatening the dependability objectives. The information contained in the gates would in addition help steer the development towards areas that needed improvement. The following are four high level conclusions to our study. First the study demonstrates a lack of consensus on mechanisms that will threaten the dependability attributes. This lack of consensus should be resolved. The lack of consensus appears for all measures to the exception of reliability. Second, measures should be developed for software availability and safety. Third, for all dependability attributes (with the exception of reliability) consistency of the measurement threads should evaluated and measurement-based development gates derived. Finally our ability to perform such type of research depends in a significant manner on access to vendor and/or utility data. The licensing environment and the first-of-a-kind nature of current software-based applications for nuclear I and C make it difficult to collect the relevant data. An approach which would either increase access to data by providing 'immunity' to the vendor or utility or the development of a software-based I and C for the sole purpose of data collection for research should be investigated. (authors)

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Refocusing an Employee Engagement Organization to Improve Participation, Member Benefits, and Impact - 19036

Washington River Protection Solutions, LLC (WRPS) provides its employees with programs and opportunities to develop professional skills and to network. Among these is an employee engagement organization called 'WRPSpeed'. WRPSpeed was founded in 2009 initially to support new employees, specifically early-career employees and those new to the Columbia Basin area surrounding the Hanford Site. It was, and remains today, an opt-in program, meaning that in order to join, employees must request to become a member; the only requirement to join is to be a WRPS employee. WRPSpeed has historically offered presentations on professional development topics along with various events and activities supporting professional networking, such as after-work-hours events and community sports teams. Since its creation, WRPSpeed has experienced an ebb and flow of interest, participation, and success. Beginning in early 2017, existing members of the WRPSpeed board examined the stagnant growth trend of the organization and determined change was needed in order to truly accomplish the mission and goals visualized by the board and by WRPS management. These changes culminated in the establishment of a new board position, Marketing and Branding, which allowed WRPSpeed to refocus their messaging and image expressed to the WRPS employee base at large. The primary objectives of the new Marketing and Branding board position were 1) to communicate the identity of WRPSpeed, 2) to communicate the benefits of participation to the WRPS employee base, and 3) to grow WRPSpeed's presence as an active community steward. During the previous years of operation, its brand had developed two main audience perception problems: a perception of exclusivity, which limited membership growth; and a lack of recognition and awareness. Though initially founded as a group for new and early-career employees, the board recognized the benefits of offering all employees the opportunity to participate. This allows more people to engage in the organization and experience the benefits, and also offers the membership and program a more robust network of professional and personal experiences and connections. Concurrent with the launch of Marketing and Branding, the WRPSpeed board reviewed their current functions and activities to determine opportunities for improvement and scale-up. The goal of this internal review was to ensure the benefits offered and advertised by WRPSpeed were high quality, valuable, and engaging. It was up to Marketing and Branding to develop strategies for the success of these efforts and reach all parties in the expanded membership. A marketing communications strategy was developed to establish a revitalized WRPSpeed image and clearly project that new image to a wider audience. The first step was to rewrite the mission statement for the organization, which established, in writing, its primary pillars: community stewardship, professional networking, and professional development. With a new mission statement and the WRPSpeed board in concurrence with - and coached on - the new image, the Marketing and Branding team launched its rebranding campaign. The campaign included a refreshed logo and theme, a new monthly newsletter for existing membership, increased and consistently stylized communications about events, a revitalized organization web page, and a ramp-up schedule for large-scale, multimedia communications to the entire company. From July 2017, when they began, to June 2018, the Marketing and Branding efforts have garnered a 20% increase in membership overall. Additionally, members surveyed in May 2018 showed 49% of respondents had been participating in WRPSpeed between 0 and 12 months; 13% responded '1-2 years'; and 38% responded '2+ years'. These results confirm an upward trend in membership, and attendance records show an increase in new people attending events. Also, parallel increases in number and quality of activities and increases in networking with employee groups from other local companies such as Bechtel National, Inc. and AECOM have improved member satisfaction and positive word of mouth among the employee population. As with any organization, employee engagement-and-retention groups like WRPSpeed face the challenges of staying relevant and beneficial to existing members while continuing to grow their program and impact. However, employee engagement organizations also have the unique opportunity to connect employees across the company and to provide them opportunities otherwise unavailable via other programs. Often these groups also have the flexibility to tailor the offerings, events, and activities to suit the specific needs and aspirations of the employees. With this exceptional position, it is important to continue to strive to offer high quality, significant, and useful benefits to the employees and, thus, the company. The strategies and campaigns employed to revitalize WRPSpeed have proven exceptionally effective in-house and are useful to other employee groups as templates for their own improvement and as opportunities for benchmarking. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Metal Bioavailability and Ecotoxicity of Bioremediated Oils and Tailings by BioTiger{sup TM}, a Microbial Consortium

Oil Sands and Mature Fine Tailings: Oil sand reserves are a major source of oil for the United States. Oil sands are a mixture of sand, clay, water, and bitumen. The refining process requires large volumes of water and generates hazardous Mature Fine Tailings (MFTs) that are stored in engineered settling ponds. They are of major environmental concern due to their persistence and difficulty to naturally biodegrade. MFT Contaminants of Concern: Naphthenic Acids (NAs), Polycyclic Aromatic Hydrocarbons (PAHs), Benzene, Toluene, Ethylbenzene and Xylene (BTEX), Metals, Residual Bitumen. BioTiger{sup TM} (BT{sup TM}), the SRNL patented 12 component microbial consortia was found to cometabolically degrade some NAs and PAHs. Previous studies performing short term exposure (48 hours and 7 days) to BT{sup TM} have resulted in increased toxicity due to the partial degradation of PAHs forming toxic intermediates. Objective: Evaluate the ecotoxicity of BT{sup TM} remediated MFTs exposed to a 2 week period w/ yeast (Y) extract. This work will determine BT{sup TM}'s remediation of MFTs from Fort McMurray, Alberta. Acute toxicity tests will be performed under section 9 of EPA's Method for Measuring Acute Toxicity using the freshwater organism, Ceriodaphnia dubia. Monitor BT{sup TM} growth through Most Probable Number (MPN) counts, pH, and metal bioavailability will also be evaluated. Preparing tailing solutions for biodegradation: BT{sup TM} components were grown in R2A media and combined. Mother BT{sup TM} was centrifuged at 7000 rpm for 20 minutes and resuspended in Bushnell Haus. 33 g of tailings were added to 1100 mL Bushnell Haus along with yeast extract (11 g) to create a 3% tailing solution. Treatments were performed in triplicate. Preparing solutions for toxicity tests using C. dubia: Supernatant was collected immediately after centrifuging at 7000 rpm for 20 min. Supernatant was filtered via a 0.22 μm sterile system. All treatments except MFT, Y peaked at T=4. This decrease in microbial growth could be associated with toxicity from intermediate byproducts. Treatments containing only MFTs decreased in the initial 11 days before growing significantly. Final solution for MFT, Y treatment had the highest pH. This could potentially be due to increased microbial activity linked with yeast consumption. All treatments except MFT, Y peaked at T=4. This decrease in microbial growth could be associated with toxicity from intermediate byproducts. Treatments containing only MFTs decreased in the initial 11 days before growing significantly. Future Direction: Await results from Acute Toxicity Tests and Metal Bioavailability Quantification of biosurfactant production. Evaluate hydrocarbon degradation byproducts using an analytical chemistry approach. More toxicity experiments with variations in time and conditions.

54 ENVIRONMENTAL SCIENCES↗

Analysis of Material Properties of Aged Rigid Polyurethane Foam

Foams are classified as either rigid or flexible and are commonly used in applications such as pipe insulation, carpet fibers, and chair foam cushions. Polyurethane foams are excellent thermal insulators, have excellent mechanical properties, and are chemically inert. With the addition of fire protective additives, polyurethane foams have the ability to intumescence when exposed to high temperatures. For the future storage of the 9977 nuclear shipping packages, the material properties of the General Plastics 3716 rigid polyurethane foam were evaluated for long term performance by comparing aged samples to unaged samples. General Plastics 3716 rigid polyurethane foam was aged from November 2014 to June 2019 at varying temperatures of: 160 deg. F, 160 deg. F + 50% relative humidity (RH), 185 deg. F, 215 deg. F, and 250 deg. F. The foam was then analyzed via Fourier Transform Infrared Spectroscopy (FTIR), 3D Optical Microscope, Thermal Gravimetric Analysis (TGA), Differential Scanning Calorimetry (DSC). FTIR and Optical Microscope: No significant change to chemical or physical structure was evident by FTIR or optical microscope analysis. DSC: Decrease of heat capacity over time for all oven temperatures except a slight increase for the 185 deg. F conditioned foams. Largest decrease evident with foams conditioned at 250 deg. F. A slight increase in heat capacity for humid samples. Similar trends in heat capacities at 71 deg. C and 102 deg. C. TGA: As conditioning temperature increased, a decline was evident in the average percent weight loss, onset temperature, and first derivative peak temperature. No significant effect due to humidity except for a decrease in first derivative peak temperature. Unaged samples exhibited strong intumescence. Foams conditioned at 160 deg. F exhibited slight intumescence. Results suggest fire protective additives decomposed at higher temperatures, which contributed to a lower average percent mass loss in higher temperature conditioning. Further thermal degradation testing would be beneficial to evaluate the ability of the conditioned foams to intumesce. Evaluate irradiation dose rate effects on conditioned foam. Possible conditioning in an environment with a known humidity or analyzing a new aliquot of sample for each trial to achieve a more representative heat capacity calculation.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Verification of Reactor Activation Modelling with Physical Characterization Data and the Impact on Long Term Assessments - 20303

Whiteshell Laboratories, located in Manitoba, Canada, provided research facilities for the Canadian nuclear industry since the early 1960's. The facility was centered on Whiteshell Reactor 1 (WR-1), an organically cooled, heavy water moderated nuclear reactor. WR-1 was safely shut down in 1985, defueled and drained, and has been in a safe Storage with Surveillance (Deferred Decommissioning) state until present day. In support of an Environmental Assessment for proposed in-situ disposal of WR-1, detailed characterization information regarding the reactor core components (calandria, calandria tubes, and pressure tubes) was necessary to provide confidence that the long-term impacts of the facility can be assessed adequately. A simplified estimate of the total activation of core components was completed in 1992 using conservative assumptions, expected reactor configuration and computer models built with WIMS-CRNL, ONEDANT and ORIGEN-S. Due to the simplification, and age of the work, there was considerable doubt that the modelled inventory estimate of the core components was sufficient to support long-term performance modeling of the planned in-situ decommissioning. Additional data would be required to provide this confidence. Several options were considered for characterizing the WR-1 core components, but it was decided to collect only a limited number of samples in an effort to validate the 1992 simplified estimate as bounding. The limited number of samples reduced risks to workers, both radiological and non-radiological, and significantly reduced the costs required to confidently define and bound the radiological inventory of activation products in the core. The results of the sampling were compared to the simplified activation estimation. There was good agreement between the modelled and sampled results, with all major contributors to total activity showing similar relative quantities. The samples were generally lower than predicted by the models, with few exceptions. Notable exceptions included Nb-94, which were higher in the sample results than the model. This was determined to be caused by the use of Niobium containing steel alloys in the stainless steel pressure tube that were not accounted for in the models. The comparison of results provided confidence that the original inventory estimates produced through the simplified model are conservative and bounding, and therefore suitable for use in the long-term assessment of in situ disposal of the WR-1 reactor. This paper provides details of the simplified computer model results, their comparison to results of the sampling, and the changes adopted in the assessment of the in-situ decommissioning of WR-1 as a result. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Post Irradiation Examination Results of Irradiated Yttrium Hydride

Department of Energy’s (DOE’s) Microreactor program (MRP) aims to provide the fundamental data to enable the development of microreactors. As such, material property data of critical materials for microreactor technologies are researched. Because substoichiometric yttrium dihydride (YHx, where x<2) is considered as a potential solid neutron moderator, its material property data has been combined in the Advanced Moderator Material Handbook which includes thermodynamic and thermophysical properties of YHx with the exception of irradiated material’s properties due to limited PIE. To fill the knowledge gap for the irradiated YHx, specimens and irradiation capsules were prepared at Los Alamos National Laboratory (LANL). Specimens were irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory’s (INL’s). post-irradiation examination (PIE) was performed at INL’s Materials and Fuels Complex (MFC). This report compiles the PIE results of irradiated YHx specimens through fiscal years 2022 and 2023 (FY22-23) . The PIE data will directly be incorporated into the newer version of the Advanced Moderator Material Handbook. The main takeaways include that (i) the geometrical stability and mechanical integrity of YHx was intact with couple exceptions after high-temperature irradiations (600-800°C), (ii) hydrogen content variation due to manufacturing or irradiation in YHx caused visible surface discoloration, that is also related to the microstructural changes, (iii) qualitative comparisons of PIE methods implied that H retention was significantly higher at 600°C as compared to 800°C, (iv) thermal properties included signatures correlated with the H loss or re-gain, (v) importance of manufacturing readiness and initial as-manufactured specimens history was emphasized, (vi) the needs of targeted irradiations focusing on temperature and time parameters and very targeted PIE were specified.

08 HYDROGEN↗

Report on the Incorporation of Post-Irradiation Examination Results of Yttrium Hydride for Advanced Moderator Handbook

Department of Energy’s (DOE’s) Microreactor program (MRP) aims to provide the fundamental data to enable the development of microreactors. As such, material property data of critical materials for microreactor technologies are researched. Because substoichiometric yttrium dihydride (YHx, where x<2) is considered as a potential solid neutron moderator, its material property data has been combined in the Advanced Moderator Material Handbook which includes thermodynamic and thermophysical properties of YHx with the exception of irradiated material’s properties due to limited PIE. To fill the knowledge gap for the irradiated YHx, specimens and irradiation capsules were prepared at Los Alamos National Laboratory (LANL). Specimens were irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory’s (INL’s). post-irradiation examination (PIE) was performed at INL’s Materials and Fuels Complex (MFC). This report compiles the PIE results of irradiated YHx specimens through fiscal years 2022 and 2023 (FY22-23) . The PIE data will directly be incorporated into the newer version of the Advanced Moderator Material Handbook. The main takeaways include that (i) the geometrical stability and mechanical integrity of YHx was intact with couple exceptions after high-temperature irradiations (600-800°C), (ii) hydrogen content variation due to manufacturing or irradiation in YHx caused visible surface discoloration, that is also related to the microstructural changes, (iii) qualitative comparisons of PIE methods implied that H retention was significantly higher at 600°C as compared to 800°C, (iv) thermal properties included signatures correlated with the H loss or re-gain, (v) importance of manufacturing readiness and initial as-manufactured specimens history was emphasized, (vi) the needs of targeted irradiations focusing on temperature and time parameters and very targeted PIE were specified.

08 HYDROGEN↗

Successful cognitive aging is associated with thicker anterior cingulate cortex and lower tau deposition compared to typical aging

INTRODUCTION There is no consensus on either the definition of successful cognitive aging (SA) or the underlying neural mechanisms. METHODS We examined the agreement between new and existing definitions using: (1) a novel measure, the cognitive age gap (SA-CAG, cognitive-predicted age minus chronological age), (2) composite scores for episodic memory (SA-EM), (3) non-memory cognition (SA-NM), and (4) the California Verbal Learning Test (SA-CVLT). RESULTS Fair to moderate strength of agreement was found between the four definitions. Most SA groups showed greater cortical thickness compared to typical aging (TA), especially in the anterior cingulate and midcingulate cortices and medial temporal lobes. Greater hippocampal volume was found in all SA groups except SA-NM. Lower entorhinal 18 F-Flortaucipir (FTP) uptake was found in all SA groups. DISCUSSION These findings suggest that a feature of SA, regardless of its exact definition, is resistance to tau pathology and preserved cortical integrity, especially in the anterior cingulate and midcingulate cortices. Highlights: Different approaches have been used to define successful cognitive aging (SA). Regardless of definition, different SA groups have similar brain features. SA individuals have greater anterior cingulate thickness and hippocampal volume. Lower entorhinal tau deposition, but not amyloid beta is related to SA. A combination of cortical integrity and resistance to tau may be features of SA.

60 APPLIED LIFE SCIENCES↗

Phase I/II Study of Radiofrequency Ablation for Malignant Renal Tumors: Japan Interventional Radiology in Oncology Study Group 0701

PurposeThis multicenter phase I/II study evaluated the safety, feasibility, and initial efficacy of radiofrequency ablation (RFA) for small malignant renal tumors.MethodsThirty-three patients were enrolled in the study. A single session of RFA was performed in patients with a renal tumor of 1–3 cm in greatest diameter, with the exception of lesions adjacent to the renal hilum. The primary endpoint was the safety of renal RFA, and the secondary endpoints were its feasibility and initial efficacy for local control, as well as the incidence and grade of adverse events. Clinical efficacy was evaluated by CT scans within 1 week and at a further 4 weeks after the procedure using the criteria adapted from the Response Evaluation Criteria in Solid Tumors.ResultsThe RFA procedure was completed in 100 % (95 % confidence interval [CI] 89–100 %) of all 33 patients. There were no severe adverse events (0 % [95 % CI 0–11 %]). Among the 33 patients, a complete response, partial response, progressive disease, and stable disease were seen in 28 (85 %), 0 (0 %), one (3 %), and one (3 %) patient(s), respectively, with a tumor response rate of 85 % [95 % CI 68–95 %]). Three patients (9 %), including one ineligible patient (3 %), were not evaluable. Out of 30 evaluable patients, a complete response was achieved in 28 (93 %).ConclusionThe current multicenter trial revealed that RFA is a safe, feasible, and effective treatment for small malignant renal tumors in patients who are not candidates for surgery.

62 RADIOLOGY AND NUCLEAR MEDICINE↗

Synthesis, characterization, and thermodynamic study of selected K-based zeolites

Potassium-rich zeolites often occur in cementitious systems, as K{sup +} is widespread in various cementitious materials, such as Portland, blended and alkali-activated cements. The knowledge of their stability and of thermodynamic models for solid solutions with Na{sup +} and Ca{sup 2+} are critical to understand long-term development and durability in such cements. Completing previous studies on Na- and Ca-based zeolites, the current work aims to determine the thermodynamic data of 14 types of K-based zeolites, which could possibly form in cementitious systems. The zeolites were synthesized hydrothermally, exchanged with K{sup +}, and characterized thoroughly with respect to framework structures, elemental compositions, water contents, and bond variations. Their thermodynamic properties were derived from the experimental solubility data, which allowed establishing predominance diagrams in the K{sub 2}O-SiO{sub 2}-Al{sub 2}O{sub 3}-H{sub 2}O system. The K-based zeolites typically showed the lowest solubility between 0 and 100 °C, with the notable exception of Ca-gismondine and two Na-based zeolites: natrolite and Na-mordenite.

36 MATERIALS SCIENCE↗

Second Solid Cancers After Radiation Therapy: A Systematic Review of the Epidemiologic Studies of the Radiation Dose-Response Relationship

Rapid innovations in radiation therapy techniques have resulted in an urgent need for risk projection models for second cancer risks from high-dose radiation exposure, because direct observation of the late effects of newer treatments will require patient follow-up for a decade or more. However, the patterns of cancer risk after fractionated high-dose radiation are much less well understood than those after lower-dose exposures (0.1-5 Gy). In particular, there is uncertainty about the shape of the dose-response curve at high doses and about the magnitude of the second cancer risk per unit dose. We reviewed the available evidence from epidemiologic studies of second solid cancers in organs that received high-dose exposure (>5 Gy) from radiation therapy where dose-response curves were estimated from individual organ-specific doses. We included 28 eligible studies with 3434 second cancer patients across 11 second solid cancers. Overall, there was little evidence that the dose-response curve was nonlinear in the direction of a downturn in risk, even at organ doses of ≥60 Gy. Thyroid cancer was the only exception, with evidence of a downturn after 20 Gy. Generally the excess relative risk per Gray, taking account of age and sex, was 5 to 10 times lower than the risk from acute exposures of <2 Gy among the Japanese atomic bomb survivors. However, the magnitude of the reduction in risk varied according to the second cancer. The results of our review provide insights into radiation carcinogenesis from fractionated high-dose exposures and are generally consistent with current theoretical models. The results can be used to refine the development of second solid cancer risk projection models for novel radiation therapy techniques.

62 RADIOLOGY AND NUCLEAR MEDICINE↗

Hyperintensity in the Dentate Nucleus on Nonenhanced T1-Weighted Magnetic Resonance Imaging Suggests Dechelation of Contrast Agents

With the exception of renal failure patients, gadolinium-based contrast agents (GBCAs) for magnetic resonance imaging (MRI) have a high tolerance and acceptability in patients needing to undergo an enhanced MRI. Now that enhanced MRIs are becoming increasingly popular and nephrogenic systemic fibrosis cases are becoming a rarity, a common belief is that these GBCAs are essentially “biologically inert” materials. However, recent reports have emerged querying the link between these GBCAs and hyperintensity in the dentate nucleus on unenhanced T1-weighted MRI in some patients. This review article outlines the basic chemistry and characteristics of currently approved GBCAs, summarizes the described research findings of gadolinium deposition in the dentate nucleus, and identifies areas for future research.

62 RADIOLOGY AND NUCLEAR MEDICINE↗

Krypton charge exchange cross sections for Hall effect thruster models

Following discharge from a Hall effect thruster, charge exchange occurs between ions and un-ionized propellant atoms. The low-energy cations produced can disturb operation of onboard instrumentation or the thruster itself. Charge-exchange cross sections for both singly and doubly charged propellant atoms are required to model these interactions. While xenon is the most common propellant currently used in Hall effect thrusters, other propellants are being considered, in particular, krypton. We present here guided-ion beam measurements and comparisons to semiclassical calculations for Kr{sup +} + Kr and Kr{sup 2+} + Kr cross sections. The measurements of symmetric Kr{sup +} + Kr charge exchange are in good agreement with both the calculations including spin-orbit effects and previous measurements. For the symmetric Kr{sup 2+} + Kr reaction, we present cross section measurements for center-of-mass energies between 1 eV and 300 eV, which spans energies not previously examined experimentally. These cross section measurements compare well with a simple one-electron transfer model. Finally, cross sections for the asymmetric Kr{sup 2+} + Kr {yields} Kr{sup +} + Kr{sup +} reaction show an onset near 12 eV, reaching cross sections near constant value of 1.6 A{sup 2} with an exception near 70-80 eV.

74 ATOMIC AND MOLECULAR PHYSICS↗

Topology breaking of the vortex in multiferroic Y{sub 0.67}Lu{sub 0.33}MnO{sub 3}

Although topological defects, such as domain walls (DWs) or vortices, are naturally protected by topological invariance, yet, we discover an exception that the six-state topology of the vortex with Z2 × Z3 symmetry is broken by a partial edge dislocation (PED) in hexagonal Y{sub 0.67}Lu{sub 0.33}MnO{sub 3}, where the topologies of the four-state vortex or closed DWs emerges. Using aberration-corrected scanning transmission electron microscopy, we found that the PED plays an important role in changing the phase of translation domain. The PED at the vortex core leads to the formation of the four-state vortex, while the ones at closed DWs connect different types of DWs, both corresponding to continuous phase changes. These results indicate that PEDs can change the topology of translation-related domain vortices and more vortices with even domains can be expected.

75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND↗

Effect of disorder on the magnetic properties of cubic Mn{sub 2}Ru{sub x}Ga compounds: A first-principles study

We perform first-principles electronic structure calculations to explain the anomalous magnetic behavior of the Mn{sub 2}Ru{sub x}Ga compounds upon Ru doping as shown experimentally recently by Kurt et al. [Phys. Rev. Lett. 112, 027201 (2014)]. Our results suggest that disorder caused by the distribution of the Mn and Ru atoms at various sites reproduces the experimental data. All compounds present antiparallel alignment of the neighboring Mn magnetic moments and, with the exception of Mn{sub 2}RuGa, none of them presents half metallic behavior.

75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND↗