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All sourcesNASA NTRSDOE OSTI
DOE OSTI2012

Research and Development of a Low Cost Solar Collector

This is a Final Technical Report on the Research and Development completed towards the development of a Low Cost Solar Collector conducted under the DOE cost-sharing award EE-0003591. The objective of this project was to develop a new class of solar concentrators with geometries and manufacturability that could significantly reduce the fully installed cost of the solar collector field for concentrated solar thermal power plants. The goal of the project was to achieve an aggressive cost target of $\$$170/m 2 , a reduction of up to 50% in the total installed cost of a solar collector field as measured against the current industry benchmark of a conventional parabolic trough. The project plan, and the detailed activities conducted under the scope of the DOE Award project addressed all major drivers that affect solar collector costs. In addition to costs, the study also focused on evaluating technical performance of new collector architectures and compared them to the performance of the industry benchmark parabolic trough. The most notable accomplishment of this DOE award was the delivery of a full-scale integrated design, manufacturing and field installation solution for a new class of solar collector architecture which has been classified as the Bi-Planar Fresnel Collector (BPFC) and may be considered as a viable alternative to the conventional parabolic trough, as well as the conventional Fresnel collectors. This was in part accomplished through the design and development, all the way through fabrication and test validation of a new class of Linear Planar Fresnel Collector architecture. This architecture offers a number of key differentiating features which include a planar light-weight frame geometry with small mass-manufacturable elements utilizing flat mirror sections. The designs shows significant promise in reducing the material costs, fabrication costs, shipping costs, and on-site field installation costs compared to the benchmark parabolic trough, as well as the conventional Fresnel collector. The noteworthy design features of the BPFC architecture include the use of relatively cheaper flat mirrors and a design which allows the mirror support beam sections to act as load-bearing structural elements resulting in more than a 36% reduction in the overall structural weight compared to an optimized parabolic trough. Also, it was shown that the utilization of small mass-produced elements significantly lowers mass-production and logistics costs that can more quickly deliver economies of scale, even for smaller installations while also reducing shipping and installation costs. Moreover, unlike the traditional Fresnel trough the BPFC architecture does not require complex articulating drive mechanisms but instead utilizes a standard parabolic trough hydraulic drive mechanism. In addition to the development of the Bi-Planar Fresnel Collector, an optimized conventional space-frame type parabolic trough was also designed, built, analyzed and field-tested during the first phase of this award. The design of the conventional space-frame parabolic collector was refined with extensive FEA and CFD analysis to reduce material costs and re-designed for simpler fabrication and more accurate lower-cost field assembly. This optimized parabolic trough represented an improvement over the state-of-the art of the traditional parabolic trough architecture and also served as a more rigorous and less subjective benchmark that was used for comparison of new candidate design architectures. The results of the expanded 1 st phase of the DOE award project showed that both the Optimized Parabolic Trough and the new Bi-Planar Fresnel Collector design concepts failed to meet the primary objectives for the project of achieving a 50% cost reduction from the industry reference total installed cost of $\$$350/m 2 . Results showed that the BPFC came in at projected total installed cost of $\$$237/m 2 representing a 32% savings compared to the industry benchmark conventional parabolic trough. And the cost reduction obtained by the Optimized Parabolic Trough compared to the industry benchmark reference was approximately 16.5% against the industry benchmark. The new BPFC design showed a weight savings of almost 36% compared to the optimized parabolic trough and a 50% reduction in field assembly labor and a 13% reduction in shipping volume. The BPFC design showed only a marginal improvement of 16% over the fully projected installed cost of the optimized parabolic trough benchmark developed as Concept One. During the course of the investigation numerous sensitivity analyses and other analytical studies were conducted to assess potential improvement opportunities, and further optimizations that could lead to cost reductions and performance improvements. Factors that could have a significant impact on high-volume costs were related to production and further improvements in design for manufacturability, automation, assembly jigs, and fixtures, and robotic welding etc. The wind modeling analysis showed that the Fresnel design concept did not reduce the wind load in a significant manner. The stress analysis showed that the design concept with almost a 36% lower weight than the parabolic trough and it was strong enough to withstand the expected wind loads and maintain targeting accuracy. The Initial on-sun optical testing showed that the Fresnel Trough was capable of concentrating sunlight effectively to the desired target and yielding an optical efficiency slightly lower than a parabolic trough.

14 SOLAR ENERGY↗
DOE OSTI2012

An Analysis of Electrostatic Discharge Considerations in the Use of Sodium Bicarbonate Media for De-Potting Sensitive Electronic Assemblies

Sodium bicarbonate blast media offers superior performance in removing low-to-medium density polyurethane foam potting materials from electronic assemblies compared to conventional abrasive or other low-hardness blast media. This work identifies a class of processing equipment suitable for potting removal in electronic assemblies and provides a technical evaluation of appropriate process controls that significantly reduce the potential for Electrostatic Discharge (ESD) degradation or damage. Once appropriate process controls are added, the class of blast equipment demonstrated here, previously used only for non-ESD sensitive assemblies, can be safely used to provide new capabilities for component-level support. In many cases, assemblies that have been de-potted using sodium bicarbonate can be disassembled and rebuilt using normal production processes, enabling repair, reacceptance, and surveillance of assemblies that was previously impractical. This paper presents the results of a study that identifies significant process variables and their contribution to ESD generation. Data are presented to quantify process-related peak ESD voltages and mitigation methods. A discussion of how to implement practical ESD controls and de-potting process test methodologies is provided. The intent of this work is to document foundational experimental work that provides a technical basis for sodium bicarbonate as an ESD-safe material for use in de-potting processes when appropriate controls are implemented.

Kinzel, Robert L.↗
DOE OSTI2021

Proposed Risk-Informed Regulatory Framework for Approval of Microreactor Transportation Packages

Microreactors are very small nuclear reactors with a power output of about 20 megawatts electric or less that are designed to be factory-built, modular in nature, and highly portable. These compact reactors will be small enough to be transported by truck or even air and could help solve energy challenges in a number of areas, ranging from remote commercial or residential locations to military bases. Pacific Northwest National Laboratory is tasked to develop and evaluate transportation licensing options for microreactors. The work is funded by the National Reactor Innovation Center a National Department of Energy program led by Idaho National Laboratory for the Office of Nuclear Energy Research and Development which support demonstration of microreactor technology. Key transportation steps include the (1) initial movement of high-assay low enriched uranium fresh fuel, (2) transportation of an intact, but never-operated microreactor, and (3) transportation of an intact, previously-operated microreactor. The deliverables on the project consists of a documentation of applicable regulations and regulatory authority for transportation. The objective of this report is to propose a risk-informed regulatory framework for the licensing of the transportation of microreactors, including the transportation of irradiated nuclear fuel that is assumed to be an integral component of the microreactor transportation package. The framework lays out a viable regulatory pathway, including decision points for regulatory options and the supporting technical evaluations for those options in phases from near to long term. This report includes discussion of the (1) general microreactor design concepts including representative microreactor source terms, (2) options for regulatory approval of microreactor transportation based on current regulation and historical precedence, (3) regulatory basis for including risk information in microreactor transportation licensing activities, and (4) description of a risk-informed regulatory framework.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2021

Proposed Risk-Informed Regulatory Framework for Approval of Microreactor Transportation Packages

Microreactors are very small nuclear reactors with a power output of about 20 megawatts electric or less that are designed to be factory-built, modular in nature, and highly portable. These compact reactors will be small enough to be transported by truck or even air and could help solve energy challenges in a number of areas, ranging from remote commercial or residential locations to military bases. Pacific Northwest National Laboratory is tasked to develop and evaluate transportation licensing options for microreactors. The work is funded by the National Reactor Innovation Center a National Department of Energy program led by Idaho National Laboratory for the Office of Nuclear Energy Research and Development which support demonstration of microreactor technology. Key transportation steps include the (1) initial movement of high-assay low enriched uranium fresh fuel, (2) transportation of an intact, but never-operated microreactor, and (3) transportation of an intact, previously-operated microreactor. The deliverables on the project consists of a documentation of applicable regulations and regulatory authority for transportation. The objective of this report is to propose a risk-informed regulatory framework for the licensing of the transportation of microreactors, including the transportation of irradiated nuclear fuel that is assumed to be an integral component of the microreactor transportation package. The framework lays out a viable regulatory pathway, including decision points for regulatory options and the supporting technical evaluations for those options in phases from near to long term. This report includes discussion of the (1) general microreactor design concepts including representative microreactor source terms, (2) options for regulatory approval of microreactor transportation based on current regulation and historical precedence, (3) regulatory basis for including risk information in microreactor transportation licensing activities, and (4) description of a risk-informed regulatory framework.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2025

Gas-Cooled High-Temperature Pebble-Bed Reactor Reference Plant Model Updates

This work presents the latest improvements to, and investigations performed with, the pebble-bed high-temperature gas-cooled reactor (PB-HTGR) reference plant models for the United States Nuclear Regulatory Commission. These models serve as the foundation for the future development of detailed design evaluation models based on license applications. The reference plant models have been developed with the Comprehensive Reactor Analysis Bundle, or BlueCRAB, which is the code suite proposed for non-light-water reactor systems safety analysis. It incorporates various simulation tools developed by the Nuclear Energy Advanced Modeling and Simulation program, including the Griffin code for reactor physics, the Pronghorn and SAM codes for core thermal fluids, the BISON code for solid conduction and fuel performance, and the SAM code for system analysis. The primary objective of the work that was performed was to assess BlueCRAB’s level of readiness for modeling a PB-HTGR. To do so, we first developed numerical models in BlueCRAB that include the key physics for this technology to ensure an adequate level of fidelity for modeling PB-HTGR core performance and for performing multiphysics simulations for equilibrium core conditions and different accident scenarios. Then we simulated transient scenarios, including depressurized and pressurized loss of forced cooling accidents, over-cooling, and control rod withdrawal events with delayed and prompt supercritical reactivity insertions. The analysis in this report includes comparisons of the 2D thermal fluid porous media models in Pronghorn and SAM, and comparisons of coupled SAM/Griffin/SAM and coupled Pronghorn/Griffin for depressurized and pressurized loss of forced cooling, over-cooling, and control rod withdrawal events. In addition, we compare 3D, 2D, and 0D/PKE neutronic models for the two control rod withdrawal scenarios with coupled Pronghorn/Griffin. The comparisons show that the BlueCRAB models lead to physically intuitive solutions for the scenarios examined. The changes in the various scalar and vector fields, such as neutron flux, power, temperature, density, pressure, and velocity, are within the expected ranges, and their distributions can be explained by the system response of the transients and the geometric and material variations. Several comparisons suggest that the porous media models in Pronghorn and SAM can lead to similar solutions, even though they are based on different methodologies. This work further highlights the need for flexible tools with various levels of fidelity to cover the breadth and depth of needs that may arise in future technical evaluations of the PB-HTGR. We believe that the BlueCRAB capabilities will be a significant asset for confirmatory analyses in order to resolve important safety questions.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2025

Fluoride-Cooled High-Temperature Pebble-Bed Reactor Reference Plant Model Updates

This work presents the latest improvements to, and investigations performed with, the Fluoride-Cooled High-Temperature Pebble-Bed Reactor reference plant models for the United States Nuclear Regulatory Commission. These models, developed with the Comprehensive Reactor Analysis Bundle, or BlueCRAB, serve as the foundation for the future development of detailed design evaluation models based on license applications. BlueCRAB is the code suite proposed for non-light-water reactor systems safety analyses, and it incorporates various simulation tools developed by the Nuclear Energy Advance Modeling and Simulation program, including the Griffin code for reactor physics, the Pronghorn and SAM codes for core thermal fluids, the BISON code for solid conduction and fuel performance, and the SAM code for system analysis. The primary objective of this work is to assess the level of readiness of BlueCRAB for modeling fluoride-cooled high-temperature pebble-bed reactors. We first developed numerical models in BlueCRAB that include the key physics for this technology, ensuring an adequate level of fidelity for modeling the core performance during accident scenarios. This was followed by simulation of transient scenarios, two loss-of-forced-cooling events (one protected and one unprotected), and two control rod withdrawal events (one delayed and one prompt supercritical reactivity insertion). The analysis includes comparisons between the 2-D thermal fluid porous media models in Pronghorn and SAM, comparisons between coupled Pronghorn-Griffin and coupled SAM-Griffin models for two loss-of-forced cooling events and one control rod withdrawal event, and comparisons between SAM single-solve and domain-overlapping approaches for multi-scale thermal fluid coupling. In addition, we performed comparisons between 3-D, 2-D, and 0-D neutronic models for the two control rod withdrawal scenarios with Pronghorn-Griffin. The results show that the BlueCRAB models led to physically intuitive solutions for the scenarios examined. The changes in the various scalar and vector fields such as the neutron flux, power, temperatures, densities, pressures, and velocities are all within the expected ranges, and their distributions can be explained from the system response of the transients and the geometric and material variations. Several comparisons suggest that the porous media models in Pronghorn and SAM can lead to similar solutions, even though they are based on different methodologies. The simulations demonstrate that there are differences between the various levels of fidelity, and it is advisable to have flexible tools that can cover the breadth and depth of needs that may arise in future technical evaluations. We believe that BlueCRAB’s capabilities represent a significant asset for confirmatory analyses aimed at resolving important safety questions.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2015

Transjugular Intrahepatic Portosystemic Shunt Placement During Pregnancy: A Case Series of Five Patients

Background and AimsComplications of portal hypertension, such as variceal hemorrhage and ascites, are associated with significant increases in both mortality and complications during pregnancy. Transjugular intrahepatic portosystemic shunt (TIPS) is a well-established procedure for treating portal hypertension, but the safety of TIPS during pregnancy is largely unknown. In this series, we review five patients who underwent TIPS placement while pregnant and describe their clinical outcomes.MethodsFive pregnant patients with cirrhosis and portal hypertension underwent elective TIPS for complications of portal hypertension (four for secondary prevention of variceal bleeding and one for refractory ascites). Outcomes measured were recurrent bleeding episodes or need for further paracenteses during pregnancy, estimated radiation dose to the fetus and gestational age at delivery. All patients were followed after delivery to evaluate technical and clinical success of the procedure.ResultsAll five patients survived pregnancy and went on to deliver successfully. When TIPS was performed for secondary prevention of variceal bleeding (n = 4), no patients demonstrated variceal bleeding after TIPS placement. When TIPS was performed for refractory ascites (n = 1), no further paracenteses were required. All patients delivered successfully, albeit prematurely. Average radiation dose estimated to the fetus was 16.3 mGy.ConclusionsThis series suggests that TIPS can be performed in selective pregnant patients with portal hypertension, with little added risk to the mother or fetus.

62 RADIOLOGY AND NUCLEAR MEDICINE↗
DOE OSTI2016

Percutaneous Transluminal Angioplasty for Complete Membranous Obstruction of Suprahepatic Inferior Vena Cava: Long-Term Results

PurposeTo determine the long-term results of percutaneous transluminal angioplasty (PTA) for a complete membranous obstruction of the suprahepatic inferior vena cava.MethodsPatients (n = 65) who were referred to the interventional unit for PTA for a complete membranous obstruction of the suprahepatic inferior vena cava between January 2006 and October 2014 were included in the study. Thirty-two patients (18 males, 14 females, mean age 35 ± 10.7, range 20–42 years) were treated. The patients presented with symptoms of ascites (88 %), pleural effusion (53 %), varicose veins (94 %), hepatomegaly (97 %), abdominal pain (84 %), and splenomegaly (40 %). Transjugular liver access set and re-entry catheter were used to puncture and traverse the obstruction from the jugular side. PTA balloon dilations were performed. The mean follow-up period was 65.6 ± 24.5 months. The objective was to evaluate technical success, complications, primary patency, and clinical improvement in the symptoms of the patients.ResultsThe technical success rate was 94 %. In two patients, obstruction could not be traversed. These patients underwent cavoatrial graft bypass surgery. There were no procedure-related complications. Clinical improvements were achieved in all patients within 3 months. The primary patency rate at 4 years was 90 %. There was no primary assisted patency. There was no need for metallic stent deployment in the cohort. The secondary patency rate at 4 years was 100 %.ConclusionsPercutaneous transluminal angioplasty for a complete membranous obstruction of the suprahepatic inferior vena cava is safe and effective, and the long-term results are excellent.

62 RADIOLOGY AND NUCLEAR MEDICINE↗
DOE OSTI2020

Technologies and policies to decarbonize global industry: Review and assessment of mitigation drivers through 2070

Fully decarbonizing global industry is essential to achieving climate stabilization, and reaching net zero greenhouse gas emissions by 2050–2070 is necessary to limit global warming to 2 °C. This paper assembles and evaluates technical and policy interventions, both on the supply side and on the demand side. It identifies measures that, employed together, can achieve net zero industrial emissions in the required timeframe. Key supply-side technologies include energy efficiency (especially at the system level), carbon capture, electrification, and zero-carbon hydrogen as a heat source and chemical feedstock. There are also promising technologies specific to each of the three top-emitting industries: cement, iron & steel, and chemicals & plastics. These include cement admixtures and alternative chemistries, several technological routes for zero-carbon steelmaking, and novel chemical catalysts and separation technologies. Crucial demand-side approaches include material-efficient design, reductions in material waste, substituting low-carbon for high-carbon materials, and circular economy interventions (such as improving product longevity, reusability, ease of refurbishment, and recyclability). Strategic, well-designed policy can accelerate innovation and provide incentives for technology deployment. High-value policies include carbon pricing with border adjustments or other price signals; robust government support for research, development, and deployment; and energy efficiency or emissions standards. These core policies should be supported by labeling and government procurement of low-carbon products, data collection and disclosure requirements, and recycling incentives. In implementing these policies, care must be taken to ensure a just transition for displaced workers and affected communities. Similarly, decarbonization must complement the human and economic development of low- and middle-income countries.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗
DOE OSTI2017

Sewage sludge disposal strategies for sustainable development

The main objective of the present review is to compare the existing sewage sludge management solutions in terms of their environmental sustainability. The most commonly used strategies, that include treatment and disposal has been favored within the present state-of-art, considering existing legislation (at European and national level), characterization, ecotoxicology, waste management and actual routs used currently in particular European countries. Selected decision making tools, namely End-of-waste criteria and Life Cycle Assessment has been proposed in order to appropriately assess the possible environmental, economic and technical evaluation of different systems. Therefore, some basic criteria for the best suitable option selection has been described, in the circular economy “from waste to resources” sense. The importance of sewage sludge as a valuable source of matter and energy has been appreciated, as well as a potential risk related to the application of those strategies. - Highlights: • Environmental sustainability in sewage sludge management. • Investigation of eco-innovations in wastewater treatment. • Assessment of ecological consequences of sewage sludge disposal.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2013

Phase 1 Clinical Trial of Stereotactic Body Radiation Therapy Concomitant With Neoadjuvant Chemotherapy for Breast Cancer

Purpose: Stereotactic body radiation therapy (SBRT) allows stereotactic irradiation of thoracic tumors. It may have a real impact on patients who may not otherwise qualify for breast-conserving surgery. We conducted a phase 1 trial that tested 5 dose levels of SBRT concomitant with neoadjuvant chemotherapy (NACT) before to surgery. The purpose of the current dose escalation study was to determine the maximum tolerable dose of SBRT in the treatment of breast cancer. Methods and Materials: To define toxicity, we performed dermatologic examinations that included clinical examinations by 2 separate physicians and technical evaluations using colorimetry, dermoscopy, and skin ultrasonography. Dermatologic examinations were performed before NACT, 36 and 56 days after the beginning of NACT, and before surgery. Surgery was performed 4 to 8 weeks after the last chemotherapy session. Efficacy, the primary endpoint, was determined by the pathologic complete response (pCR) rate. Results: Maximum tolerable dose was not reached. Only 1 case of dose-limiting toxicity was reported (grade 3 dermatologic toxicity), and SBRT was overall well tolerated. The pCR rate was 36%, with none being observed at the first 2 dose levels, and the highest rate being obtained at dose level 3 (25.5 Gy delivered in 3 fractions). Furthermore, the breast-conserving surgery rate was up to 92% compared with an 8% total mastectomy rate. No surgical complications were reported. Conclusions: This study demonstrates that SBRT can be safely combined with NACT. Regarding the efficacy endpoints, this trial showed promising results in terms of pCR rate (36%) and breast-conserving rate (92%). The findings provide a strong rationale for extending the study into a phase 2 trial. In view of the absence of correlation between dose and pCR, and given that the data from dose level 3 met the statistical requirements, a dose of 25.5 Gy in 3 fractions should be used for the phase 2 trial.

62 RADIOLOGY AND NUCLEAR MEDICINE↗
DOE OSTI2026

Effect of spacer grids on high-burnup fuel fragmentation, relocation, and dispersal

Increasing the fuel burnup limit in light-water reactors to improve fuel cycle economics requires a strong technical foundation. Experimental observations from the Halden and Studsvik programs have revealed severe fuel fragmentation during loss-of-coolant accident (LOCA) conditions, highlighting the need for additional technical evaluation. Consequently, further LOCA test data are needed to complement existing findings and improve the understanding of fuel fragmentation, relocation, and dispersal (FFRD) behavior. Oak Ridge National Laboratory’s Severe Accident Test Station has played a significant role in advancing the understanding of high-burnup fuel fragmentation, relocation, and dispersal phenomena. One remaining gap in the available experimental database is the effect of fuel assembly structural features on cladding deformation behavior during a LOCA, and more specifically, their impact on the fuel’s ability to fragment, relocate, and disperse. Recent analyses using the BISON fuel performance code suggest that cladding deformation near grid spacers will remain below the 3% threshold that has been reported in the NRC Research Information Letter, indicating that the cladding could remain mechanically constrained during the LOCA event. This paper builds upon the BISON analyses to design and conduct a series of out-of-cell tests aimed at further evaluating cladding deformation in and around grid spacers. In addition, these tests were used to assess local cladding temperature conditions and compare them against analytical predictions in order to better replicate expected in-reactor behavior. Finally, an in-cell high-burnup LOCA test was designed and performed to evaluate the effects of a grid spacer, or cladding restraint, on fuel fragmentation, relocation, and dispersal susceptibility. The high-burnup test results differed from those of historical LOCA experiments, with a recorded rupture temperature of 861°C. Two ballooned regions and corresponding rupture openings were observed, with rupture widths of approximately 0.64 mm for both ruptures and rupture lengths of 4.8 mm and 5.6 mm, respectively.

Capps, Nathan [ORNL]↗
DOE OSTI2012

Technical Basis for DOE Standard 3013 Equivalency Supporting Reduced Temperature Stabilization of Oxalate-Derived Plutonium Oxide Produced by the HB-Line Facility at Savannah River Site

The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO 2 ) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO 2 feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO 2 (i.e., 950 °C for 2 hours) preclude use of the HBL PuO 2 in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO 2 that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO 2 from oxalate precipitation processes from 950 °C to 640 °C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 °C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 µg/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 µg/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013 equivalency. Under the defined process conditions and associated material specifications, the high-purity PuO 2 produced in HBL presents no unique safety concerns for packaging or storage in the 3013 required configuration. The PuO 2 produced using the HBL flow sheet conditions will have a higher specific surface area (SSA) than PuO 2 stabilized at 950 °C and, consequently, under identical conditions will adsorb more water from the atmosphere. The greatest challenge to HBL operators will be controlling moisture content below 0.5 wt %. However, even at the 0.5 wt % moisture limit, the maximum acceptable pressure of a stoichiometric mixture of hydrogen and oxygen in the 3013 container is greater than the maximum possible pressure for the HBL PuO 2 product.

08 HYDROGEN↗
DOE OSTI2013

Assessment of Offshore Wind Energy Leasing Areas for the BOEM Massachusetts Wind Energy Area

The U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL), under an interagency agreement with the Bureau of Ocean Energy Management (BOEM), is providing technical assistance to identify and delineate leasing areas for offshore wind energy development within the Atlantic Coast Wind Energy Areas (WEAs) established by BOEM. This report focuses on NREL's development of three delineated leasing area options for the Massachusetts (MA) WEA and the technical evaluation of these leasing areas. The overarching objective of this study is to develop a logical process by which the MA WEA can be subdivided into non-overlapping leasing areas for BOEM's use in developing an auction process in a renewable energy lease sale. NREL worked with BOEM to identify an appropriate number of leasing areas and proposed three delineation alternatives within the MA WEA based on the boundaries announced in May 2012. A primary output of the interagency agreement is this report, which documents the methodology, including key variables and assumptions, by which the leasing areas were identified and delineated.

17 WIND ENERGY↗
DOE OSTI2015

Structural Health and Prognostics Management for Offshore Wind Plants (Final Report)

This final report is a compilation of research efforts – funded by the US Department of Energy Wind and Water Power Technologies Office over a four-year period from FY11 through FY14. The goals of this research program were to develop and evaluate technical innovations with promise for maximizing revenues and reducing levelized cost of energy (LCOE) for offshore wind plants – more specifically the goals of the Structural Health and Prognostics Management (SHPM) program were to reduce O&M costs and increase energy capture through use of SHPM-based technologies. A technology roadmap was developed at the start of the project to guide the research efforts. This roadmap identified and outlined six major research thrust areas each having five stages of maturity. Research was conducted in each of these thrust areas, as documented throughout this report, although a major focus was on development of damage detection strategies for the most frequent blade damage conditions and damage mitigation and life-extension strategies via changes in turbine operations (smart loads management). The work summarized in this compilation report is the product of the work of many researchers. A summary of the major findings, status of the SHPM Technology Roadmap and recommendations for future work are also provided.

17 WIND ENERGY↗
DOE OSTI2017

Cherokee Wind Energy Development - Feasibility and Pre-Construction Studies

Cherokee Nation Businesses (CNB) received a grant from the US Department of Energy to explore feasibility and pursue development of a wind power generation facility on Cherokee land in north-central Oklahoma. This project followed several years of initial study exploring the possibility of commercial-scale wind power generation on primarily agricultural land owned by the Cherokee Nation. This project produced detailed analysis of the legal, financial and market viability of such generation facilities, and encompassed a full technical evaluation of the engineering, environmental, and geotechnical aspects of installing this capacity. During the course of this project, information gleaned from this exploration changed CNB’s thinking about the best course of action for Cherokee participation in the development, eventually moving away from an equity-owner model and towards utilization of the land asset as a resource while mitigating Cherokee financial and operational risk.

17 WIND ENERGY↗
DOE OSTI2017

ATF-1 Power Histories

MCNP5 calculated ATF-1 power histories are documented in this Technical Evaluation (TEV). The current revision of this TEV (Revision 0), includes power histories through Advanced Test Reactor (ATR) Cycle 162A. The Cycle 162A power histories are based off projection calculations while all other cycles are based off as-run (core follow) simulations. This TEV will serve as the single source for ATF-1 experiment power history information and will be updated after each cycle of operation.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Fracture Mechanics Analysis of Isotope Fuel Impact Tester, Milli-Watt, Multi-Hundred Watt and GPHS Outer Catch-Tube Subassembly Design

The Isotope Fuel Impact Tester (IFIT) at PF-4 is a specialized set of equipment designed for simulating high-speed impact of experimental parts. The IFIT is an inert gas launcher designed to impact 238 PuO 2 heat source assemblies, fuel encapsulation materials, structural materials, and subassemblies of radioisotope thermoelectric generators (RTGs). TA-55 management desires to re-use outer catch tube (OCT) of the milli-watt (MW), multi-hundred watt (MHW) and general purpose heat source (GPHS) designs and thus requires a technical evaluation of potential life cycles to failure. This report provides a fitness-for-service (FFS) assessment using fracture mechanics techniques based on the state-of-stress developed with the aid of a computational finite element model (FEM) of the IFIT. Importantly, the report describes the different material options for the OCT; H-11 vacuum-arc re-melted (VAR) and H-13 VAR for a given heat treatment resulting in a Rockwell-C hardness of 42, and an additional option of 4340 alloy steel with a range of heat treatment resulting in Rockwell-C hardness of 40 to 44.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗