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At least 811 records · Page 45
All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

MIS High-Purity Plutonium Oxide Metal Oxidation Product TS707001 (SSR123): Final Report

A high-purity plutonium dioxide material from the Material Identification and Surveillance (MIS) Program inventory has been studied with regard to gas generation and corrosion in a storage environment. Sample TS707001 represents process plutonium oxides from several metal oxidation operations as well as impure and scrap plutonium from Hanford that are currently stored in 3013 containers. After calcination to 950°C, the material contained 86.98% plutonium with no major impurities. This study followed over time, the gas pressure of a sample with nominally 0.5 wt% water in a sealed container with an internal volume scaled to 1/500th of the volume of a 3013 container. Gas compositions were measured periodically over a six year period. The maximum observed gas pressure was 138 kPa. The increase over the initial pressure of 80 kPa was primarily due to generation of nitrogen and carbon dioxide gas in the first six months. Hydrogen and oxygen were minor components of the headspace gas. At the completion of the study, the internal components of the sealed container showed signs of corrosion, including pitting.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2017

NXIS - Well integrity inspection in unconventional gas wells

The objective of this project is to advance the state-of-the-art and to develop an integrity inspection system capable of detecting physical flaws in the wellbore structure of conventional and unconventional hydrocarbon producing wells. Measuring the integrity of multiple wellbore casings and cement annuli for onshore and offshore wells remains a challenging task. We propose a multi-modality inspection system composed of neutron and X(gamma)-ray imaging modalities (nXis) to address the above challenge. The functional principle of this wellbore integrity inspection system is the combination of high-energy modalities, such as X(gamma)-ray and neutron backscatter imaging, with conventional low-energy modalities, such as electromagnetic or ultrasound imaging techniques. By combining multiple sensing modalities into one sensing system and by fusing data between modalities, one can gather more information about the integrity of the wellbore structure compared to simply using multiple sensors individually. Imaging prototypes for gamma, neutron, and electromagnetics were designed, manufactured, and tested at GE Global Research and Starfire Industries. Wellbore phantoms with engineered defects were manufactured and the performance of the developed wellbore integrity inspection tool prototypes was evaluated in a test pit test at an industrial GE Oil & Gas facility. Data analysis and fusion between various inspection techniques show enhanced defect detectability. These exciting results were presented at various technical conferences and discussed with operators in the oil & gas industry. Great interest from oil operators lead to discussions about joint industrial partnerships to move the developed technology from the prototype phase to the product phase.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2018

Microscopic Examination of the Corroded Hagan Container Used to Store Molten Salt Extraction Residue XBPS333

A microscopic examination was performed on a Hagan container after corrosion and a white powder were found on the outside surface of the lid and filter cover while in storage in the vault. The inside surfaces of the container were covered by a wipeable brown coating. The coating was removed and portions of the container were sectioned and imaged with optical microscopy. General corrosion was found throughout the inside of the container, and pitting corrosion was observed in several locations on the lid and sidewall. This report describes the type and extent of the corrosion observed and its impact on the storage lifetime of the container.

36 MATERIALS SCIENCE↗
DOE OSTI2018

ARIES Oxide Production Program at LANL

Disassemble pits from stockpile-return units identified as excess by NA-23 and convert metal to oxide.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

ARIES Blend Lot Book Data Analysis

The Advanced Recovery Integrated Extraction System (ARIES) Program being executed at Los Alamos TA-55 produces unpolished plutonium oxide powder from pit disassembly in batches of material referred to as a blend lot. Each blend lot is sampled and analyzed by Los Alamos group C-AAC (Chemistry Division, Actinide Analytical Chemistry Group) for radioactive and nonradioactive constituents contained in the material. A blend lot, which nominally consists of 12 kg(Pu), is then packaged into three DOE-STD-3013 containers that are analyzed by nondestructive analysis (NDA) to determine the fraction and total amount of plutonium mass relative to impure plutonium oxide. The analytical and NDA data are presented in a Blend Lot Book (BLB). The data are used to confirm that a blend lot grouping of three cans meets the requirements for off-site shipment specified in the formal interface control document (ICD). The analytical and NDA data from 49 blend lots were reviewed to provide summary-level information on the constituents present in the blend lots. The results provide an overall perspective in historical amounts for constituent averages over all blend lots and similar information in the variation between constituent levels. Note that to properly compare the can contents, it would be most appropriate to decay all of cans’ constituents to a particular date. Previously, this analysis only examined statistical data as determined at the time of blend lot chemical analysis. The chemical analysis dates span the period from June 2011 to May 2015 (4 years), which is 28% of one Pu-241 half-life. Therefore, the approximate nature of the aggregate information must be properly understood in this light. However, to address this issue, a new table is included in this revision that decays the 48 blend lots to a single date.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
DOE OSTI2018

Updated Erosion Analysis for Material Disposal Area G, Technical Area 54, Los Alamos National Laboratory

Material Disposal Area G (MDA G), located within Technical Area 54 (TA-54) is used to dispose radioactive waste at Los Alamos National Laboratory (LANL). Technical Area 54 is located on LANL property on the Pajarito Plateau between the communities of Los Alamos and White Rock (Figure 1-1). The MDA G disposal facility is currently in operation (Figure 1-2). Waste is generally placed in large rectangular pits, numbered 1-39, and cylindrical shafts within MDA G.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada: For Calendar Year 2017, Revision 0

This report serves as the combined annual report for post-closure activities for the following closed corrective action units (CAUs): CAU 90, Area 2 Bitcutter Containment; CAU 91, Area 3 U-3fi Injection Well CAU 92, Area 6 Decon Pond Facility; CAU 110, Area 3 WMD U-3ax/bl Crater; CAU 111, Area 5 WMD Retired Mixed Waste Pits; and, CAU 112, Area 23 Hazardous Waste Trenches. The results of the inspections, a summary of maintenance activities, and an evaluation of monitoring data are presented in this report. Site inspections are conducted annually at CAUs 90, 91, and 112; semiannually at CAUs 92 and 110; and quarterly at CAU 111. Additional inspections are conducted at CAU 92 if precipitation occurs in excess of 1.0 inches in a 24-hour period and at CAU 111 if precipitation occurs in excess of 1.0 inch in a 24-hour period. Inspections include an evaluation of the condition of the units, including covers, fences, signs, gates, and locks. At CAU 110, soil moisture monitoring, vegetation evaluations, and subsidence surveys are conducted in addition to the visual inspections. At CAU 111, soil moisture monitoring, vegetation evaluations, subsidence surveys, direct radiation monitoring, air monitoring, radon flux monitoring, and groundwater monitoring are conducted. This report will address all monitoring items notes above except groundwater monitoring. Groundwater monitoring is documented in the Nevada National Security Site Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site. All required inspections, maintenance, and monitoring were conducted in accordance with the post-closure requirements of the permit. Revision 4 of Permit NEV HW0101 was issued effective December 10, 2015, and remains in effect until December 10, 2020.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2015

Chemical Free Surface Processing for High Gradient Superconducting RF Cavities

Chemical treatment such as buffered chemical polishing (BCP) or electro polishing (EP) followed by high pressure rinsing (HPR) of niobium (Nb) superconducting RF (SRF) cavities is expensive and complex multistep process. Furthermore, the cavity RF surfaces after the treatment still have numerous bubbles and pits that result from welding. These quench-producing weld defects together with the particulate contamination, result in significant scatter of the multi-cell Nb SRF cavities performance characteristics. This scatter is the major problem in the current manufacturing of the Nb SRF cavities. When developed the chemical free surafce processing using IEB will benefit first J-lab's CEBAF and Fermilab's Project X. Also, light sources, require 1.3 - 1.5 GHz SRF structures. Furthermore, IEB will produce much broader impact because it can be implemented into manufacturing of many other types of RF devices including both superconducting as well as normal conducting RF cavities. This program will develop a new process that will enhance quality of the superconducing radio-frequency cavities and allow acceleration of charged particles to much higher energies. The process also will improve the cavity manufacturing and result in substantial cost reduction of superconducting radio-frequency high-energy particle accelerators. Niobium samples were successfully processed by a DC electron beam to a degree that is suitable for the interior surface of an SRF cavity. To accomplish this, a complete system was developed from the ground up. A vacuum chamber system was acquired and adapted to act as the vessel for performing the Nb processing experiments. An extremely robust high voltage power supply was developed and manufactured to provide the power necessary to drive the multi-kW DC electron gun. A high voltage isolation filament transformer was also designed and manufactured to provide the necessary current to drive the filament within the electron gun. Finally, a beam melt characterization DC electron gun was created. This gun was used to explore the parameter space of interest for processing Nb SRF cavities. The beam melt characterization tests concluded that multiple quick passes at moderate beam power provided the most ideal melt zone characteristics Nb surfaces. It was also found that excellent melt and polish results could be achieved at lower voltages than originally conceived, getting the great results at a beam voltage of 20kV versus the 50kV used in the initial Phase I testing at Jefferson Laboratory. Operating at 20kV will also greatly reduce the challenges of designing a compact DC electron gun for processing of complete Nb SRF cavities, which will be done in Phase III. This final report is divided in eight parts which cover the major investigation work and results which have been performed and achieved. The first part addresses the design, fabrication and testing of the vacuum chamber. In the second part, the DC power supply output circuit design is presented for providing an operating space of 50-60kV with currents from 20-160mA and short and open circuit fault modes are considered and resolved. The third section covers testing and commissioning of the high voltage step up transformer and 150kV isolation transformer. Section four covers the design, construction and performance for a 100kV high voltage bushing. Section number five treats the filament design and load testing. Section number six covers electron gun design and simulation of electron beam melting. Section seven presents the beam target design, assembly and testing and test gun with solenoid magnet, design, fabrication and testing. Finally, section eight demonstrates electron beam melting and polishing of Nb, Cu and SS samples.

75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND↗
DOE OSTI2018

Aging Hanford Nuclear Waste and Simulants Using Carbon Dioxide to Evaluate Corrosion at Lower pH Limits

Carbon dioxide gas was used to mimic the environmental chemistry that takes place as air contacts the surface layer of the waste solutions. Carbon dioxide acts as an acid in tank waste and has an affinity to the high pH solutions. Sodium hydroxide (a base) is added to tank waste according to waste handling specifications. This reagent is added in order to keep the tank metal protected from pitting corrosion. Problems that arise with performing sodium hydroxide additions are that volumes in some tanks are currently approaching capacity and every addition adds to the waste volume needing to be removed in order to close Hanford.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Hanford Tank Waste Disposition Integrated Flowsheet: Corrosion Specification Development Final Report

The Savannah River National Laboratory has developed a corrosion model to facilitate implementation of Hanford’s Direct Feed Low Activity Waste flowsheet. The focus was specifically on secondary effluent waste stream compositions from the Hanford Waste Treatment and Immobilization Plant’s melter off-gas treatment system returned to the Hanford Tank Farms (return stream.) The return stream compositions were predicted to contain components at relative concentrations that are significantly more corrosive toward the carbon steel waste tanks, specifically halide and sulfate anions, than the current waste compositions in the tank farms. Electrochemical tests were performed, utilizing a statistically designed matrix, to determine the corrosion chemistry limits that will mitigate pitting in the return stream. The current corrosion chemistry specifications for the Hanford Tank Farms do not mitigate for the halide concentrations that will be expected in the return stream. The model requires a 10:1 nitrite to total halide ratio, for stream compositions at a minimum of pH 10 and a maximum temperature of 40°C. The final specification may use other corrosion data that is being generated for the DST chemistry control limits to delineate between the effect of fluoride and chloride. This test program has employed statistically designed test matrices and electrochemical test methods to validate the corrosion model specifically at boundary regions to optimize corrosion control specifications.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Global Survey of Selected Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges(Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D):A Guide

This report presents tables, references, notes, and a synthesis of some notable geotechnical and engineering information that were applied in the creation of five interactive layer maps [http://gis.inl.gov/globalsites/ will redirect to 2018 update, http://gis.inl.gov/GlobalSurvey/] for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies or disposal facilities 3) deep large diameter boreholes, 4) physics underground laboratories and facilities, and 5) deep open pit mines from around the world. These data are intended to facilitate user access to basic information and references regarding “deep underground” facilities, history, activities, and plans. In general, the interactive maps and database provide each facility’s approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not all encompassing, it is a comprehensive review of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The interactive map suite allows for a better appreciation of site area geographic and cultural settings. The global survey is intended to be used as a communication tool to support and inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development applicable to any mined geologic disposal facility as a demonstration (examples) of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

MIS High-Purity Uranium/Plutonium Oxide Metal Oxidation Product SCP711-56 (SSR135): Final Report

A high-purity uranium/plutonium mixed oxide material from the Material Identification and Surveillance (MIS) Program inventory has been studied with regard to gas generation and corrosion in a storage environment. Sample SCP711-56 represents process plutonium oxides from mixed oxides at the Hanford Site, byproduct plutonium/uranium mixed oxides at the Rocky Flats Plant, Hanford Site mixed oxides at Savannah River, mixed oxides from alloy oxidation at Savannah River, scrap mixed oxides at Savannah River and plutonium/uranium oxide at Los Alamos National Laboratory that are currently stored in 3013 containers. After calcination to 950°C the material contains 17% fuel grade plutonium and 68% uranium with approximately 1.5% impurities and the remainder principally oxygen. This study followed over time the gas pressure of a sample with nominally 0.1 wt% water in a sealed container with an internal volume scaled to 1/500th of the volume of a 3013 container. Gas compositions were measured periodically over approximately 4 years. The maximum observed gas pressure was 115 kPa. The increase over the initial pressure of 83 kPa was primarily due to generation of carbon dioxide and nitrogen gases. A small amount of hydrogen was generated and oxygen was consumed. At the completion of the study, the internal components of the sealed container showed signs of corrosion, including pitting.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

MIS High Purity Plutonium Oxide Metal Oxidation Product MT1490 (SSR125): Final Report

A high purity plutonium dioxide material from the Material Identification and Surveillance (MIS) Program inventory has been studied with regard to gas generation and corrosion in a storage environment. Sample MT1490 represents process plutonium oxides from several metal oxidation operations that are currently stored in 3013 containers. This study followed over time, the gas pressure of a sample with nominally 0.5 weight percent water in a sealed container with an internal volume scaled to 1/500 th of the volume of a 3013 container. The sample was a mixture of as-received material, material calcined at 800°C and material calcined at 950°C. This material contained 87% plutonium with no major impurities. Gas compositions were measured periodically over a nine year period. The maximum observed gas pressure of 118 kPa was reached during the ninth year. The increase over the initial pressure of 95 kPa was primarily due to generation of nitrogen and hydrogen gas. Oxygen was a minor component of the headspace gas. At the completion of the study, the inner bucket showed signs of corrosion, including pitting, in the container material contact region.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2014

Neutron Fluences for EBR-II Reflector Assemblies U9902, U9003, U9005, U9006 and U9027

There are currently five complete Experimental Breeder Reactor No. 2 (EBR-II) reflector assemblies being stored in the Hot Fuel Examination Facility (HFEF) pits at Idaho National Laboratory (INL); these are reflector assemblies U9902, U9003, U9005, U9006 and U9027. Reflector assembly U9027 was fabricated with a 12% cold-worked Type 316 steel can and Type 304 steel blocks, while the other assemblies had Type 304 steel cans and blocks. There has been interest at INL in using these irradiated reflector (steel) assemblies to correlate observed material damage to exposure (fluence, i.e., flux times time), and to do this, spatial neutron fluence levels for each of these reflector assemblies needs to be known. The irradiation histories of these five reflector assemblies, in terms of EBR-II grid positions and Run cycles, are shown in Table 1. This data was obtained from the “SASBLY” file in the EBR-II Physics Analysis Database (PADB) which gives positional and run information for each assembly irradiated in the EBR-II. Except for short-term storage in the blanket region (position 13D8), all relevant reflector assemblies were irradiated in either EBR-II hex-row 9 or 10.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2019

Aging Hanford Nuclear Waste and Simulants Using Carbon Dioxide to Evaluate Corrosion at Lower pH Limits

Carbon dioxide gas was used to mimic the environmental chemistry that takes place as air contacts the surface layer of the waste solutions. Carbon dioxide acts as an acid in tank waste and has an affinity to the high pH solutions. Sodium hydroxide (a base) is added to tank waste according to waste handling specifications. This reagent is added in order to keep the tank metal protected from pitting corrosion. Problems that arise with performing sodium hydroxide additions are that volumes in some tanks are currently approaching capacity and every addition adds to the waste volume needing to be removed in order to close Hanford.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Evolving Grid Services, Products, and Market Opportunities for Regulated Electric Utilities

This report and policy brief focus on the more recent changes and evolutions in grid services, products, and market opportunities regulated electric utilities are offering to their customers, both traditional end-use electric customers as well as third-party party businesses. Drawing on a database of more than 50 recent examples, the most prevalent and significant evolutions are occurring in: residential retail rate design shifts toward voluntary and default time-of-use (TOU); changes to distributed generation (DG) compensation methodologies; utilization of customer and non-utility assets as non-wires alternatives (NWAs); and utility investments in electric vehicle (EV) infrastructure. Important and related themes emerge from this assessment of recent trends suggesting regulators and policymakers should formulate clear and consistent policy goals around the following two issues: 1. Opportunities increasing competition to serve the electricity needs of retail customers. Reforms that drive increases in NWAs and DG pit utility investments against customer investments and may erode the exclusivity of the utility franchise. In contrast, reforms to DG compensation, that may reduce the financial benefits of a customer’s investment, may maintain or strengthen the firmness of the utility franchise boundaries. 2.Opportunities driving greater innovation within and outside the electric industry. Electric utilities are innovating by developing novel NWA opportunities that can provide financial support for the broader adoption of DERs. There are also electric utility efforts to enable broader innovation in other industries, where utility investment in EV charging infrastructure could promote greater EV ownership and enable utility control of these resources to provide grid services.

24 POWER TRANSMISSION AND DISTRIBUTION↗
DOE OSTI2019

Report for the Corrosion Testing of Solutions to Aid in the Removal of 241-AP-106 Waste: Dilution Series Testing

Corrosion analyses were conducted at the 222-S Laboratory in support of proposed liquid waste removal from tank 241-AP-106 (AP-106) in preparation for its use in direct feed low activity waste treatment. The work reported here builds upon previous corrosion testing performed at the 222-S Laboratory that used a high-density caustic and an AP-106 tank waste sample. In this current study, a second liquid grab sample from AP-106 was diluted, 50:50 vol%, with raw water, and this dilution was repeated for a total of 5 dilutions steps. Following each dilution step, the resulting solution was tested for pitting corrosion using linear polarization resistance followed by cyclic potentiodynamic polarization.

241-AP-106↗
DOE OSTI2019

Post-Closure Report for Closed Resource Conservation and Recovery Act Corrective Action Units, Nevada National Security Site, Nevada: For Calendar Year 2018 (Revision 0)

This report serves as the combined annual report for post-closure activities for the following closed corrective action units (CAUs): CAU 90, Area 2 Bitcutter Containment; CAU 91, Area 3 U-3fi Injection Well; CAU 92, Area 6 Decon Pond Facility; CAU 110, Area 3 WMD U-3ax/bl Crater; CAU 111, Area 5 WMD Retired Mixed Waste Pits; and CAU 112, Area 23 Hazardous Waste Trenches. The locations of the sites are shown in Figure ES-1. This report covers calender year 2018. The post-closure requirements for these sites are described in Resource Conservation and Recovery Act Permit Number NEV HW0101 and are summarized in each CAU-specific section of this report. The results of the inspections, a summary of maintenance activities, and an evaluation of monitoring data are presented in this report. Site inspections are conducted annually at CAUs 90, 91, and 112; semiannually at CAUs 92 and 110; and quarterly at CAU 111. Additional inspections are conducted at CAUs 92 and 111 if precipitation occurs in excess of 1.0 inch in a 24-hour period. Inspections include an evaluation of the condition of the units, including covers, fences, signs, gates, and locks. At CAUs 110 and 111, soil moisture monitoring and subsidence surveys are conducted in addition to the visual inspections. At CAU 110 the site fence, gate, lock and use restriction signs are evaluated. At CAU 111, an ecological survey, direct radiation monitoring, air monitoring, radon flux monitoring, and groundwater monitoring are also conducted. This report will address all monitoring item notes above except groundwater monitoring. Groundwater monitoring is documented in the Nevada National Security Site Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site. All required inspections, maintenance, and monitoring were conducted in accordance with the post-closure requirements of the permit. Revision 6 of Permit NEV HW0101 was issued effective December 10, 2015, and remains in effect until December 10, 2020.

54 ENVIRONMENTAL SCIENCES↗