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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 415 records · Page 23
All sourcesNASA NTRSDOE OSTI
DOE OSTI2012

GUIDANCE FOR THE PROPER CHARACTERIZATION AND CLASSIFICATION OF LOW SPECIFIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED OBJECTS FOR DISPOSAL

Regulatory concerns over the proper characterization of certain waste streams led CH2M HILL Plateau Remediation Company (CHPRC) to develop written guidance for personnel involved in Decontamination & Decommissioning (D&D) activities, facility management and Waste Management Representatives (WMRs) involved in the designation of wastes for disposal on and off the Hanford Site. It is essential that these waste streams regularly encountered in D&D operations are properly designated, characterized and classified prior to shipment to a Treatment, Storage or Disposal Facility (TSDF). Shipments of waste determined by the classification process as Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) must also be compliant with all applicable U.S. Department of Transportation (DOE) regulations as well as Department of Energy (DOE) orders. The compliant shipment of these waste commodities is critical to the Hanford Central Plateau cleanup mission. Due to previous problems and concerns from DOE assessments, CHPRC internal critiques as well as DOT, a management decision was made to develop written guidance and procedures to assist CHPRC shippers and facility personnel in the proper classification of D&D waste materials as either LSA or SCO. The guidance provides a uniform methodology for the collection and documentation required to effectively characterize, classify and identify candidate materials for shipping operations. A primary focus is to ensure that waste materials generated from D&D and facility operations are compliant with the DOT regulations when packaged for shipment. At times this can be difficult as the current DOT regulations relative to the shipment of LSA and SCO materials are often not clear to waste generators. Guidance is often sought from NUREG 1608/RAMREG-003 [3]: a guidance document that was jointly developed by the DOT and the Nuclear Regulatory Commission (NRC) and published in 1998. However, NUREG 1608 [3] is now thirteen years old and requires updating to comply with the newer DOT regulations. Similar challenges present themselves throughout the nuclear industry in both commercial and government operations and therefore, this is not only a Hanford Site problem. Shipping radioactive wastes as either LSA or SCO rather than repacking it is significantly cheaper than other DOT radioactive materials shipping classifications particularly when the cost of packages is included. Additionally, the need to 'repackage' materials for transport can often increase worker exposure, necessitated by 'repackaging' waste materials into DOT 7 A Type A containers.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2023

DEPDOSE

DEPDOSE is an open-source computer application which combines the KDEP respiratory tract deposition software with committed equivalent dose coefficient tables from the DC_PAK internal dosimetry package. DEPDOSE allows the user to rapidly produce tables of dose coefficients to workers and members of the public inhaling a precisely defined, user-specified aerosols using the ICRP 60 series methodology. Combined with a plume dispersion modeling system such as QUIC, this makes it possible to predict radiation doses downstream from an accidental or intentional release of radioactive materials. For this work, a radioactive plume was calculated to members of the public downstream from a plausible release of radionuclides into the atmosphere.

Klumpp, John↗
DOE OSTI2016

In situ synthesis and characterization of uranium carbide using high temperature neutron diffraction

Advances in neutron flux, neutron instrumentation, and sample environments over the past years allowed the development of unique techniques to characterize material synthesis and processing. The available infrastructure at LANL allows to apply these techniques to radioactive materials or materials containing actinides. Here, we present capabilities and results to characterize materials in situ at temperatures above 2000 Celsius degrees such as in loss-of-coolant accidents. Temperatures in excess of 2000 C. degrees are not readily achieved and neutrons are one of a few probes to characterize materials under these conditions. Research in refractory materials, phase diagram studies or accident scenarios for nuclear materials are research areas where such extreme conditions are required. As an example, we present the formation of UC{sub x} from UO{sub 2+x} and graphite in situ using high temperature neutron diffraction with particular focus on resolving the conflicting reports on the crystal structure of non-quenchable cubic UC{sub 2}. The ability to follow the reaction UO{sub 2}+C → UC{sub x}+CO{sub y} in situ with neutron diffraction allows us to conclude that the reaction occurs within minutes over a temperature range of 60 Celsius degrees. The initiation of the reaction is far below the reaction temperature of 2000 C. degrees reported for this reaction in standard text books on actinide chemistry. This may be due to the unusually small ∼100 nm grain size of our UO{sub 2} initial powder. Furthermore, the holding time of several hours reported in the literature would be unnecessary. The neutron diffraction data collected for the cubic high temperature UC{sub 2} phase unambiguously confirmed the disordered C-C dumbbells and excluded structures previously determined by X-ray diffraction.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2017

Differing Approaches to the Same Destination: SRS vs. Hanford Transportation Safety Document and Onsite Transportation Program - 17142

The United States Department of Energy, DOE Order 460.1C establishes packaging and transportation requirements to ensure the safety of DOE shipments of hazardous material. In accordance with DOE Order 460.1C, there are two general ways that radioactive material can be transferred if remaining within the boundary of a DOE site (i.e., onsite): 1) Packages can be transferred fully compliant with U. S. Department of Transportation (DOT) requirements; or 2) Packages can be transferred under an appropriately approved site-specific Transportation Safety Document (TSD) DOE G 460.1-1 - The Implementation Guide for Use with DOE Order 460.1A Packaging and Transportation Safety specifies the required format, content, and approval process for TSDs, but also allows great flexibility. Although developed using the same guidance, both the Savannah River Site and Hanford Site TSD programs were developed largely independent of each other. This paper compares both programs. Although at first glance the approaches seem dauntingly different, both result in surprisingly similar equivalent safety. (authors)

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DOE OSTI2016

Natal kicks and time delays in merging neutron star binaries: implications for r-process nucleosynthesis in ultra-faint dwarfs and in the Milky Way

Merging neutron star binaries are prime candidate sources for heavy r-process nucleosynthesis. The amount of heavy r-process material is consistent with the mass ejection and rates of mergers, and abundances of relic radioactive materials suggest that heavy r-process material is produced in rare events. Observations of possible macronovae provide further support for this model. Still, some concerns remain. One is the observation of heavy r-process elements in ultra-faint dwarf (UFD) galaxies. The escape velocities from UFDs are so small that the natal kicks, taking place at neutron stars’ birth, might eject such binaries from UFDs. Furthermore, the old stellar populations of UFDs require that r-process nucleosynthesis must have taken place very early on, while it may take several Gyr for compact binaries to merge. This last problem arises also within the Milky Way where heavy r-process materials have been observed in some low-metallicity stars. We show here that ≳0.5 of neutron star binaries form with a sufficiently small proper motion to remain bound even in a UFD. Furthermore, approximately 90% of double neutron stars with an initial separation of 10{sup 11} cm merge within 300 Myr and ≈15% merge in less than 100 Myr. This population of “rapid mergers” explains the appearance of heavy r-process material in both UFDs and in the early Milky Way.

79 ASTRONOMY AND ASTROPHYSICS↗
DOE OSTI2021

Public Safety: Fighting Crime and Terrorism; Border Security

This chapter discusses risks from unintentional or illicit movement of nuclear and radioactive material out of regulatory control through international border crossing points, summarizes international efforts to build capacity and support border security, and discusses how detection equipment can be used to screen for penetrating radiation at traditional border crossing points.

border security↗
DOE OSTI2014

Separation of thorium (IV) from lanthanide concentrate (LC) and water leach purification (WLP) residue

Thorium (IV) content in industrial residue produced from rare earth elements production industry is one of the challenges to Malaysian environment. Separation of thorium from the lanthanide concentrate (LC) and Water Leach Purification (WLP) residue from rare earth elements production plant is described. Both materials have been tested by sulphuric acid and alkaline digestions. Th concentrations in LC and WLP were determined to be 1289.7 ± 129 and 1952.9±17.6 ppm respectively. The results of separation show that the recovery of Th separation from rare earth in LC after concentrated sulphuric acid dissolution and reduction of acidity to precipitate Th was found 1.76-1.20% whereas Th recovery from WLP was less than 4% after concentrated acids and alkali digestion processes. Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) was used to determine Th concentrations in aqueous phase during separation stages. This study indicated that thorium maybe exists in refractory and insoluble form which is difficult to separate by these processes and stays in WLP residue as naturally occurring radioactive material (NORM)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Special Form Testing of Sealed Source Encapsulation for High-Alpha-Activity Actinide Materials

In the United States all transportation of radioactive material is regulated by the U.S. Department of Transportation (DOT). Beginning in 2008 a new type of sealed-source encapsulation package was developed and tested by Oak Ridge National Laboratory (ORNL). These packages contain high-alpha-activity actinides and are regulated and transported in accordance with the requirements for DOT Class 7 hazardous material. The DOT provides specific regulations pertaining to special form encapsulation designs. The special form designation indicates that the encapsulated radioactive contents have a very low probability of dispersion even when subjected to significant structural events. The special form designs have been shown to simplify the delivery, transport, acceptance, and receipt processes. It is intended for these sealed-source encapsulations to be shipped to various facilities making it very advantageous for them to be certified as special form. To this end, DOT Certificates of Competent Authority (CoCAs) have been sought for the design suitable for containing high-alpha-activity actinide materials. This design consists of the high-alpha-activity material encapsulated within a triangular zirconia canister, referred to as a ZipCan, tile that is then enclosed by a spherical shell. The spherical shell design, with ZipCan tile inside, was tested for compliance with the special form regulations found in 49 CFR 173.469. The spherical enclosure was subjected to 9-m impact, 1 m percussion, and 10-minute thermal tests at the Packaging Evaluation Facility located at the National Transportation Research Center in Knoxville, TN USA and operated by ORNL. Before and after each test, the test units were subjected to a helium leak check and a bubble test. The ZipCan tiles and core were also subjected to the tests required for ISO 2919:2012(E), including a Class IV impact test and heat test and subsequently subjected to helium leakage rate tests [49 CFR 173.469(a)(4)(i)]. The impact-tile test unit contained a nonradioactive surrogate; however, the thermal test unit contained a radioactive source. This paper describes the regulatory special form tests and presents detailed impact and leak test results that demonstrate that the sealed source encapsulation designs satisfy the regulatory tests.

Martinez, Oscar A↗
DOE OSTI2012

Estimation of Internal Radiation Dose from both Immediate Releases and Continued Exposures to Contaminated Materials

A brief description is provided of the basic concepts related to 'internal dose' and how it differs from doses that result from radioactive materials and direct radiation outside of the body. The principles of radiation dose reconstruction, as applied to both internal and external doses, is discussed based upon a recent publication prepared by the US National Council on Radiation Protection and Measurements. Finally, ideas are introduced related to residual radioactive contamination in the environment that has resulted from the releases from the damaged reactors and also to the management of wastes that may be generated in both regional cleanup and NPP decommissioning.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2019

Licensing and Operation of BEA Research Reactor Package for Fuel, Source and Target Payloads - 19198

The Battelle Energy Alliance (BEA) Research Reactor Package (BRR Package) is currently in use for a variety of payload types and operational scenarios. The BRR Package is licensed by the Nuclear Regulatory Commission (NRC), under Certificate of Compliance (CoC) number USA/9341/B(U)F-96. The original packaging design, testing, and safety analysis activities were conducted by Orano Federal Services (Orano FS, formerly AREVA Federal Services) for the Idaho National Laboratory (INL), operated by the Battelle Energy Alliance (BEA) for the U.S. Department of Energy (DOE). One package was built and delivered to the INL in 2009, and has seen routine use since that time, primarily by DOE University Research Reactor programs. This paper will provide a history and description of the original design and licensing of the package and subsequent amended applications for the addition of new payloads. Each additional payload type provided unique design, operational, and licensing challenges - these challenges will be discussed, and the results and lessons learned presented will be beneficial for application in other radioactive material packaging projects. (authors)

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

Recent Regulatory Challenges Associated with Managing NORM and TENORM Waste Streams in the United States - 19609

Recent regulatory changes in several states in the United States (U.S.) have introduced new challenges to industries impacted with naturally occurring radioactive materials (NORM) and/or technologically enhanced NORM (TENORM) requiring innovative solutions. Because NORM and TENORM are specifically exempt from U.S. Nuclear Regulatory Commission (NRC) regulations, the onus falls on the 50 states to regulate their use and disposal. Over the past 10 years, regulations applying to NORM and TENORM have been drafted, passed, or updated in multiple states, including North Dakota, Pennsylvania, Illinois, and West Virginia to name a few. Solutions and lessons learned before and during the recent regulatory changes for a variety of clients, including specialty metals, mining, and oil and gas (O and G), are presented. In addition, the design and implementation of the comprehensive study of NORM/TENORM associated with conventional and unconventional O and G production activities in Pennsylvania on behalf of the Pennsylvania Department of Environmental Protection (PADEP) is presented, and the development of analytical solutions and waste processes designed to minimize the impact of the new regulations while maintaining compliance is discussed. (author)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Th and U fuel photofission study by NTD for AD-MSR subcritical assembly

During the last decade a considerable effort has been devoted for developing energy generating systems based on advanced nuclear technology within the design concepts of GEN-IV. Thorium base fuel systems such as accelerator driven nuclear reactors are one of the often mentioned attractive and affordable options. Several radiotherapy linear accelerators are on the market and due to their reliability, they could be employed as drivers for subcritical liquid fuel assemblies. Bremsstrahlung photons with energies above 5.5MeV, induce (γ,n) and (e,e’n) reactions in the W-target. Resulting gamma radiation and photo or fission neutrons may be absorbed in target materials such as thorium and uranium isotopes to induce sustained fission or nuclear transmutation in waste radioactive materials. Relevant photo driven and photo-fission reaction cross sections are important for actinides {sup 232}Th, {sup 238}U and {sup 237}Np in the radiotherapy machines energy range of 10-20 MV. In this study we employ passive nuclear track detectors (NTD) to determine fission rates and neutron production rates with the aim to establish the feasibility for gamma and photo-neutron driven subcritical assemblies. To cope with these objectives a 20 MV radiotherapy machine has been employed with a mixed fuel target. Results will support further development for a subcritical assembly employing a thorium containing liquid fuel. It is expected that acquired technological knowledge will contribute to the Venezuelan nuclear energy program.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2017

Safety analysis report for packaging shielding and nuclear criticality safety courses developed and conducted by Oak Ridge National Laboratory

The US Department of Energy (DOE) Packaging Certification Program, Office of Packaging and Transportation, is offering Safety Analysis Report for Packaging (SARP) Shielding and Nuclear Criticality Safety (NCS) courses for SARP generalists and analysts. The SARP generalist course is designed for project managers, supervisors, NCS/shielding subject matter experts (SME), and SMEs in non-NCS/shielding technical areas (e.g., structural, thermal, package design) who need to better understand how NCS/shielding analyses fit into the broader body of SARP documentation. The generalist course provides an overview of the regulations and guidelines for the criticality and shielding analyses for a SARP and illustrates how the NCS/shielding chapters integrate with the other parts of the SARP. After course material is presented, students in the generalist course will review an actual SARP document to examine key elements of the shielding and criticality analyses. The analyst course provides detailed instructions on the radioactive material package shielding analyses and NCS evaluation fundamentals needed by analysts/practitioners (i.e., safety analysts and/or technical reviewers) to prepare and/or review technical analyses for the SARP documentation. The analyst course also provides an overview of regulations and guidelines, in addition to detailed in-class exercises associated with package shielding and NCS analyses. Analysis teams will be faced with staged SARP examples in which several important decision processes in the generation of a SARP will be demonstrated and discussed. The courses are offered at Oak Ridge National Laboratory's National Transportation Research Center. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2013

Demonstration test results of organic materials' volumetric reduction using bio-ethanol, thermal decomposition and burning

To discover technologies that can be utilized for decontamination work and verify their effects, economic feasibility, safety, and other factors, the Ministry of the Environment launched the 'FY2011 Decontamination Technology Demonstrations Project' to publicly solicit decontamination technologies that would be verified in demonstration tests and adopted 22 candidates. JAEA was commissioned by the Ministry of the Environment to provide technical assistance related to these demonstrations. This paper describes the volume reduction due to bio-ethanol, thermal decomposition and burning of organic materials in this report. The purpose of this study is that to evaluate a technique that can be used as biomass energy source, while performing volume reduction of contamination organic matter generated by decontamination. An important point of volume reduction technology of contaminated organic matter, is to evaluate the mass balance in the system. Then, confirming the mass balance of radioactive material and where to stay is important. The things that are common to all technologies, are ensuring that the radioactive cesium is not released as exhaust gas, etc.. In addition, it evaluates the cost balance and energy balance in order to understand the applicability to the decontamination of volume reduction technology. The radioactive cesium remains in the carbides when organic materials are carbonized, and radioactive cesium does not transfer to bio-ethanol when organic materials are processed for bio-ethanol production. While plant operating costs are greater if radioactive materials need to be treated, if income is expected by business such as power generation, depreciation may be calculated over approximately 15 years. (authors)

09 BIOMASS FUELS↗
DOE OSTI2017

Development of Microwave Technology for TENORM Waste Treatment - 17377

The sludge and scales generated by the oil and gas industry usually contain radionuclides of the thorium and uranium decay chains, the so-called technologically enhanced, naturally occurring radioactive materials (TENORM) waste. The handling of this waste must consider both the radiation risks presented by those radionuclides and its chemical toxicity, due to the decomposition of oil residues, which may generate hydrogen sulfide and other hazardous compounds. In the case of Brazil, Public Law 10.308 limits the management options for radioactive waste generated by offshore oil production rigs to drumming and storage; it prohibits disposal of any radioactive waste in sea-waters, seabed or oceanic islands. This paper describes the results of the work to develop a treatment process using a specially designed microwave oven, which removes simultaneously water and hydrocarbons from the sludge, thus reducing the volume, the chemical toxicity and the chemical reactivity of the waste. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Initial Modeling of Urban Search Measurements

Detection of illicit nuclear materials in urban environments is difficult due to the large amount of background radiation from naturally occurring radioactive materials (NORM) in the roadways and buildings. Mobile searches suffer from low count rates, so the detection algorithms must be carefully balanced between missing real sources and reporting too many false alarms. The Modeling Urban Scenarios and Experiments (MUSE) project aims to create a virtual testbed for simulation of radiation detection to predict realistic background and threat source detection events so that detection algorithms can be better optimized to find illicit sources. The MUSE project is a collaboration of Oak Ridge National Laboratory (ORNL), Lawrence Berkeley National Laboratory (LBNL), and the Remote Sensing Laboratory (RSL). The project also works with staff at Lawrence Livermore National Laboratory (LLNL) to support the development of the Optimization Planning Tool for Urban Search (OPTUS) software package. The first step in creating a virtual testbed is to determine the level of detail required in the models to match actual measurements. Several measurement campaigns were conducted in 2015 and 2016 at the Fort Indiantown Gap (FTIG) Combined Arms Collective Traming Facility (CACTF). This facility contains a representative urban environment, with a dozen buildings and several streets. Detectors commonly used in search operations - 2 in x 4 in x 16 in NaI(Tl) - were used to measure count rates from background and sources. Measurements with a shielded high-purity germanium detector of the roadways, sidewalks, and building walls were made to determine the concentration of NORM that makes up the bulk of the background radiation. This paper shows some comparisons of modeling simulations to measurements taken during the OPTUS-3 campaign in November 2015. Measurements with and without an 81 {mu}Ci cesium source were made at several points along the center line of the main road. Initial results show good agreement between the measured and simulated spectra above 300 keV. Additional studies to determine the causes of mismatch below 300 keV have been started and will also be discussed.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2018

DETECTION OF NUCLEAR OR OTHER RADIOLOGICAL MATERIALS OUT OF REGULATORY CONTROL AS CRIMINAL/UNAUTHORIZED THREATS TO MAJOR PUBLIC EVENTS

Major Public Events (MPEs), by their nature, draw great public interest and receive intense media attention. They can be anything from sporting events (e.g., Olympics, World Cups) to political summits to large festivals. The threat of nuclear or other radiological materials out of regulatory control during these events is of particular concern. A terrorist could use this material as a dirty bomb to disperse radioactive material in a stadium, or hide dangerous radioactive sources in a garbage can to expose people to harmful radiation, leading to fear and uncertainty. The requirements for nuclear security, preparedness, and operational capabilities for nuclear/radiological detection at MPEs have steadily increased in recent years. Many countries have gained considerable experience in recent years in nuclear security operations at MPEs when hosting these events. Dozens of MPEs hosted around the world each year now provide some level of nuclear security as part of their overall security plan. Several training workshops and courses, co-sponsored by the U.S. Department of Energy / National Nuclear Security Administration and the International Atomic Energy Agency, and conducted through bilateral agreements, are offered each year. These workshops and courses provide the opportunity to share best practices and lessons learned and aid countries to build capacity for nuclear security at their MPEs. Additionally, the International Atomic Energy Agency provides guidance for the detection of radiological threat materials out of regulatory control through the Nuclear Security Systems and Measures for Major Public Events, IAEA Nuclear Security Series No. 18.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2020

Developing Materials for Extreme Environments and Their Use in Nuclear Waste Canisters and Reactors - 20559

The paper focuses on the development of materials which can be utilized in extreme industrial environments. The paper discusses the advancement of materials and their application in components which are utilized in extreme industrial environments as such that of the nuclear field and especially in the nuclear waste field. Nuclear power plants have become an indispensable part of the electricity generation, medical, food processing and many other industries. Though burning small amount of fuel as compared to conventional power plants, they also create waste which is not easy to handle as other types of wastes. The nuclear waste sitting at the bottom of spent fuel tanks around the globe has raised public concerns on how it will be dealt with. Europe has started to give an answer by working on geological repositories. Though till yet, waste has been cooled in spent fuel tanks and after processing, is precisely placed in nuclear waste canisters and casks and transported to sites across the country for further cooling and storage. Though in all this process there had been a great deal of advancement on the type of casks and canisters used and the processes for transporting nuclear material and waste. Often reports about radioactive material leakage, moisture content inside barrels etc. has surfaced. Be it official or unofficial report, there seems a technical failure on how the nuclear waste has been stored and placed at facilities around the globe. The other aspect of this material development is to be beneficial for nuclear reactors. As the technology gets advanced, nuclear reactors change their titles from Gen II to Gen III and so on. The new fleet of upcoming reactors will be exceptionally safer, reliable and more efficient. But these benefits will also bring drawbacks with them. As these reactors will operate at high temperature (above 800 degree Celsius) they also ask for advancement in materials used in the reactor core, fuel used, reactor control etc. The paper tries to answer such concerning questions. The work shows the study done on different material that can be better candidates for extreme environments. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗