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At least 19 records
All sourcesNASA NTRSDOE OSTI
DOE OSTI2022

Determination of Biogenic Content by 14 C in fuels using Liquid Scintillation Analysis Laboratory Analytical Procedure (Laboratory Analytical Procedure)

This procedure covers the determination of the percent 14 C in biogenic gasoline, jet fuel, and diesel range hydrocarbons prepared from distillation of hydrotreated pyrolysis oils and blended with fossil derived hydrocarbons (e.g. fossil diesel, gasoline, jet, or toluene). Either an internal 14C standard or a color quench curve is used to correct for potential signal quenching effects. Recent publications provide some background of direct LSC methods used for determination of biogenic fuel content.

02 PETROLEUM↗
DOE OSTI2018

Analytical Laboratory Presentation at Canadian Nuclear Laboratory

The INL Analytical Research Laboratories and the CNL Analytical Laboratories share many of the same capabilities and expertise while also overlapping significantly in mission. Where there are similarities and differences in the types of samples and analytical procedures between the two facilities, each laboratory can learn much from the other, and establish a technical baseline that may be mutually beneficial. An exchange of knowledge and exposure to the international laboratories benefits both organizations, and it is the purpose of the proposed visits to the two facilities to foster understanding and learning between the respective scientists. Topics of common interest include but are not limited to multi-collector ICP-MS; high resolution gas MS; alpha, beta, and gamma spectrometry; and separations chemistry of nuclear materials. By sharing expertise, the INL and CNL Analytical Laboratories will improve their analyses providing more reliable results and capabilities that are competitive with other world-class facilities.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2023

Determination of Total, Organic, and Inorganic Carbon and Total Nitrogen in Biological Cultures and Liquid Fraction Process Samples: Laboratory Analytical Procedure (LAP)

This Laboratory Analytical Procedure (LAP) describes the quantitative determination of total organic carbon, inorganic carbon in whole suspended biological samples and in the cell-free supernatant, by combustion and CO 2 detection with a non-dispersive infrared (NDIR) detector. This allows for distinct reporting of soluble and insoluble organic and inorganic carbon. In addition, this procedure covers the quantitative determination of soluble nitrogen in the cell-free supernatant.

09 BIOMASS FUELS↗
DOE OSTI2019

Characterization techniques for TRU waste from the Analytical Laboratory Hot Cells at Idaho National Laboratory

Characterization techniques for TRU waste from the Analytical Laboratory Hot Cells at Idaho National Laboratory Since the first reactor went hot in 1942, there has been a never ending desire to improve the nuclear reactor and the fuel that it burns. The Idaho National Laboratory has been a key player in reactor and fuel development. As more research projects begin, the spectrum of waste parameters grows. Over the years, the Analytical Laboratory (AL) at the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL) has supported a large range of various research projects. Each project brings its own challenge and analytical technique that, in turn, yields its own unique waste parameters. The AL Hot Cells at INL consist of 6 small cells that can support around 12 different fuel research projects at a time along with infrastructure and environmental samples. Each different project yields different levels of transuranic (TRU) material, RCRA constituents, dose, and contamination levels. The waste parameters from each project dictate a path forward for the waste Low-Level Waste (LLW), Contact Handled TRU (CH-TRU), Mixed Contact Handled TRU (M-CH-TRU), Remote Handled TRU (RH-TRU), or Mixed Remote Handled TRU (M-RH-TRU). With visual examination techniques and process knowledge as an aid, there have been waste handling methods developed that allow debris and sample material to be segregated. Unique characterization mechanisms have been applied for each debris and sample material that are generally more accurate than smear and surface contamination data. For debris found in the Hot Cells, analytical data is gathered and conservatively summarized for each fuel type and research method. This consists of data from Quadrupole Inductively Coupled Plasma Mass Spectrometry (Q-ICP-MS), Gamma Spectroscopy, and some data verification through Thermal Ionization Mass Spectrometry (TIMS) and Multi-Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS). This data gives a range of TRU isotope concentrations. Fuel age is taken into account to determine the dominant TRU activity isotopes. Cesium concentrations are also gathered. Each parameter/fuel type then ties a measured Cesium number to TRU content based on historical analytical data. Debris in the hot cells is segregated by project and packaged in individual 2 gallon metal paint cans. Each can is counted by gamma spectroscopy in a calculated and measured geometry. Using process knowledge to determine the fuel or project type, newly counted cesium numbers can be applied to the historic analytical data and TRU content can be estimated. The TRU content allows waste debris to be segregated between CH-TRU and RH-TRU. Packaging techniques can allow for the minimization if RH-TRU waste. Sample material received into the AL must be dissolved into a liquid matrix in order to be analyzed in most cases. When analysis is complete, these liquids go through a consolidation, complexation, neutralization, and solidification process where real time analytical data can be used to calculate TRU content and RCRA constitutes. These calculations allow for no further analytical data to be gathered. The waste matrix is considered stable and acceptable by all AK [define AK] documents. The unique techniques used in characterizing and handling the Analytical Laboratories Hot Cell waste can be applied to various situations and various laboratories. They allow for more accurate data for waste constituents and also for the minimization of RH-TRU waste.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
DOE OSTI2018

ANALYTICAL LABORATORY AT IDAHO NATIONAL LABORATORY COUNTING EQUIPMENT STANDARDIZATION AND QUALITY CONTROL IMPROVEMENT

The Analytical Laboratory at Idaho National Laboratory (INL) is a growing program with an emphasis on providing high quality results to customers, and an increasing focus on independent research. The Analytical Laboratory Counting Group has a number of capabilities: six gamma-ray counters, one gamma-ray sample changer, four gas flow proportional counter drawers, an auto-changing gas flow proportional counter, two liquid scintillation counters, and an alpha spectroscopy system. Other capabilities within the Analytical Laboratory include quadrupole inductively coupled plasma mass spectrometry (ICP-MS), high resolution ICP-MS, multi-collector ICP-MS, ICP atomic emission spectrometry (ICP-AES), gas mass spectrometry, thermal ionization mass spectrometry (TIMS), several glove boxes and fume hoods for sample preparation, and six interconnected hot cells for sample receipt and dissolution. In order to position the Analytical Laboratory as a world-class research institution, the Counting Group has recently begun making improvements to its analytical techniques, calibrations, standardization, and quality control procedures. A large part of this effort is to increase the level of documentation of instrument work. One project is to re-calibrate all of the gamma systems with newly purchased standards. One of the changes made in the purchase of the new standards was to lower the total activity so that the dead time of the calibration would more closely match the dead time of typical samples. Similarly, another planned project is to use new standards to re-calibration the gas flow proportional counters. Additional work has focused on testing and improving alpha spectroscopy sample preparation techniques. Plutonium separations have been tested to improve tracer recovery and to verify the separation technique in the presence of typical sample matrices. A final planned area of improvements has focused on liquid scintillation counting. One difficulty the Counting Group has encountered in liquid scintillation counting is an inflated gross alpha count relative to other analysis methods in the presence of high gross beta activity. Ideas include investigating the impact of choice of scintillation cocktail, as well as the effects of sample dilution.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
DOE OSTI2021

Accelerated Aging of Fast Pyrolysis Bio-Oil Using Carbonyl Titration: Laboratory Analytical Procedure (LAP)

This laboratory analytical procedure covers the accelerated aging of fast pyrolysis bio-oils. Bio-oils undergo reactions that result in physical and chemical changes over time. These changes typically result in an increase in molecular weight, decrease in some functional groups such as carbonyls, and an increase in viscosity; additionally, the aging process often leads to phase separation. Studies have shown that accelerated aging of bio-oils using this method closely mimics room temperature aging for long periods of time (over 3 years). This procedure has been developed for the accelerated aging of fast pyrolysis bio-oils only. Fast pyrolysis bio-oils are more reactive than other bio-oils (e.g., catalytic fast pyrolysis) and undergo aging much more rapidly. Therefore, this procedure should only be used for fast pyrolysis bio-oil samples.

09 BIOMASS FUELS↗
DOE OSTI2022

Identification and Quantification of Photosynthetic Pigments in Algae (Laboratory Analytical Procedure (LAP))

The Laboratory Analytical Procedure (LAP) outlined here describes a method to quantitatively extract phytopigments from microalgae biomass, as well as to identify and quantify individual pigments based on separation and detection with a High-Performance Liquid Chromatography (HPLC) system coupled to a Diode Array Detector (DAD). Pigments were extracted with greater than 95 % extraction efficiency. Chromatographic conditions allowed for isomeric resolution between pigments and identification based on UV/Vis spectra and comparison to analytical standards.

09 BIOMASS FUELS↗
DOE OSTI2020

Data review processes in the analytical laboratory

These documents contain information on the Analytical laboratory data review processes for the following analytical techniques: - alpha spectrometry - light elements analyses - gamma spectrometry - gas proportional flow counting - HR-ICP-MS - Q-ICP-MS - MC-ICP-MS - ICP OES - liquid scintillation counting

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
NASA NTRS1977

The role of light microscopy in aerospace analytical laboratories

Light microscopy has greatly reduced analytical flow time and added new dimensions to laboratory capability. Aerospace analytical laboratories are often confronted with problems involving contamination, wear, or material inhomogeneity. The detection of potential problems and the solution of those that develop necessitate the most sensitive and selective applications of sophisticated analytical techniques and instrumentation. This inevitably involves light microscopy. The microscope can characterize and often identify the cause of a problem in 5-15 minutes with confirmatory tests generally less than one hour. Light microscopy has and will make a very significant contribution to the analytical capabilities of aerospace laboratories.

Crutcher, E. R.↗
DOE OSTI2020

Automated Data Review of Analytical Laboratory Results at Los Alamos National Laboratory - 20299

Newport News Nuclear BWXT-Los Alamos, LLC (N3B) collects samples in support of the U.S. Department of Energy's (DOE) Office of Environmental Management (EM) Los Alamos Legacy Cleanup Contract (LLCC). N3B receives and reviews over 1.6 million sample data points annually in support of various ongoing environmental monitoring and remediation projects of the LLCC. N3B must demonstrate and document that reported external analytical laboratory data produced for the LLCC are of sufficient quality to fulfill their intended purpose and to support defensible decision making as described in EPA QA/G4 Guidance for the Data Quality Objectives Process 1994. In 2018, N3B assumed management of the LLCC along with the Environmental Information Management (EIM) database that contains all historical and current environmental data associated with the LLCC. The entire EIM database is shared between N3B, Triad National Security, LLC (Triad), and New Mexico Environment Department (NMED). These three parties jointly manage the database, its configuration, and changes / updates. All environmental data that are entered into EIM are updated and available, on a daily basis, in the linked public database Intellus New Mexico (Intellus). The quality and defensibility of the environmental data generated from sampling activities is a key component of an effective remediation process. Providing quality data is accomplished through a data assessment process that includes examination, verification, and validation. Examination is the assessment of completeness of the deliverables, identification of any reporting errors, and determining the usability of the data based on the laboratory's evaluation of its data as described in the case narrative received with the data. Verification consists of an evaluation of the Electronic Data Deliverables (EDD) data report to determine the extent to which the external analytical laboratories met method and contract-specific quality control and reporting requirements. Validation consists of determining the data quality and the extent to which the external analytical laboratories accurately and completely reported all sample and quality control results and satisfied all contract requirements. EIM contains an automatic Data Validation Module which performs automated data review (DVM ADR). DVM ADR is a tool to assist in the validation process. When DVM ADR is used in conjunction with manual examination of sample data packages, the combination of the two will meet and exceed the requirements of verification. N3B recognized an opportunity for process improvement, focusing on DVM ADR configuration and enhancements in EIM. Testing EIM's configuration provided proof of the DVM ADR's capabilities and flexibility to accurately perform routine data checks based on analytical methods and regulatory requirements. In addition, the DVM ADR module was improved through enhancements for all analytes, particularly upgrades for radiochemistry data. Extensive testing of the DVM ADR module occurred using EDDs from actual laboratory analyses on the EIM testing site. During this process, N3B manipulated EDD information to verify that the actual outcomes matched the expected outcomes. The results of this testing were shared with the database architects, and configuration improvements were identified to address these results. During this process, N3B identified that the radiochemical DVM ADR capabilities were underutilized, and so enhanced the DVM ADR functionality with respect to radioanalytical assessment. N3B environmental data uploads to Intellus on a daily basis from EIM, once the analytical data undergoes examination and verification. As such, it is important to have a high level of confidence in the quality and defensibility of the data. The process of manual examination, along with the DVM ADR, in conjunction with full validation of a percentage the data specified through the Data Quality Objectives greatly increases efficiency of data review and confidence level of the quality of the data, and gives the project managers, governmental offices, and the public expedited access to high-quality data. (authors)

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

Analytical Laboratory Counting and Radiochemistry Group Equipment and Capabilities

The Analytical Laboratory at the Materials and Fuels Complex provides quality analytical results through a variety of instrumental methods. The work of the Counting and Radiochemistry Group focuses on several instrumental techniques: Gamma Spectrometry, Liquid Scintillation Counting, Gas Flow Proportional Counting, and Alpha Spectrometry. This talk will focus on an overview of the Counting and Radiochemistry's capabilities, and will briefly discuss some of the sample preparation methods currently in use by the group.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Characterization Techniques for TRU Waste from the Analytical Laboratory Hot Cells at Idaho National Laboratory - 19610

Since the first reactor went hot in 1942, there has been a never ending desire to improve the nuclear reactor and the fuel that it burns. The Idaho National Laboratory has been a key player in reactor and fuel development. As more research projects begin, the spectrum of waste parameters grows. Over the years, the Analytical laboratory (AL) at the INL Materials and Fuels Complex (MFC) has supported a large range of various research projects. Each project brings its own challenge and analytical technique that, in turn, yields its own unique waste parameters. The AL Hot Cells at INL consist of 6 small cells that can support around 12 different fuel research projects at a time along with infrastructure and environmental samples. Each different project yields different levels of transuranic (TRU) material, RCRA constituents, dose, and contamination levels. The waste parameters from each project dictate a path forward for the waste as Low-Level Waste (LLW), Contact Handled TRU (CH-TRU), Mixed Contact Handled TRU (M-CH-TRU), Remote Handled TRU (RH-TRU), or Mixed Remote Handled TRU (M-RHTRU). With visual examination techniques and process knowledge as an aid, there have been waste handling methods developed that allow debris and sample material to be segregated. Unique characterization mechanisms have been applied for each debris and sample material that are generally more accurate than smear and surface contamination data. For debris found in the Hot Cells, analytical data is gathered and conservatively summarized for each fuel type and research method. This consists of data from Quadrupole Inductively Coupled Plasma Mass Spectrometry (Q-ICP-MS), Gamma Spectroscopy, and some data verification through Thermal Ionization Mass Spectrometry (TIMS) and Multi-Collector Inductively Coupled Plasma Mass Spectrometry (MC-ICP-MS). This data gives a range of TRU isotope concentrations. Fuel age is taken into account to determine the dominant TRU activity isotopes. Cesium concentrations are also gathered. Each parameter/fuel type then ties a measured Cesium number to TRU content based on historical analytical data. Debris in the hot cells is segregated by project and packaged in individual 2 gallon metal paint cans. Each can is counted by gamma spectroscopy in a calculated and measured geometry. Using process knowledge to determine the fuel or project type, newly counted cesium numbers can be applied to the historic analytical data and TRU content can be estimated. The TRU content allows waste debris to be segregated between CH-TRU and RH-TRU. Packaging techniques can allow for the minimization of RHTRU waste. Sample material received into the AL must be dissolved into a liquid matrix in order to be analyzed in most cases. When analysis is complete, these liquids go through a consolidation, complexation, neutralization, and solidification process where real time analytical data can be used to calculate TRU content and RCRA constitutes. These calculations allow for no further analytical data to be gathered. The waste matrix is considered stable and acceptable by all Acceptable Knowledge (AK) documents. The unique techniques used in characterizing and handling the Analytical Laboratories Hot Cell waste can be applied to various situations and various laboratories. They allow for more accurate data for waste constituents and also for the minimization of RH-TRU waste. (authors)

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

Gamma Spectrometry Inside an Analytical Laboratory Hot Cell

One of the unique capabilities of the Analytical Laboratory at the Materials and Fuels Complex is the ability to analyze samples in-cell by gamma spectrometry. This presentation will discuss some of the challenges inherent to gamma spectrometry in high-background areas, as well as some of the advantages to in-cell counting.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2021

Lessons Learned-Analytical Laboratory Construction Modifications

The purpose of this document is to disseminate lessons learned from the Sandia National Laboratories (SNL) Building 1090 modification project and other analytical laboratory related construction projects. The following sections summarize lessons learned at various phases of the project.

99 GENERAL AND MISCELLANEOUS↗
NASA NTRS1979

Automating the Analytical Laboratories Section, Lewis Research Center, National Aeronautics and Space Administration: A feasibility study

The feasibility of computerized automation of the Analytical Laboratories Section at NASA's Lewis Research Center was considered. Since that laboratory's duties are not routine, the automation goals were set with that in mind. Four instruments were selected as the most likely automation candidates: an atomic absorption spectrophotometer, an emission spectrometer, an X-ray fluorescence spectrometer, and an X-ray diffraction unit. Two options for computer automation were described: a time-shared central computer and a system with microcomputers for each instrument connected to a central computer. A third option, presented for future planning, expands the microcomputer version. Costs and benefits for each option were considered. It was concluded that the microcomputer version best fits the goals and duties of the laboratory and that such an automted system is needed to meet the laboratory's future requirements.

Boyle, W. G.↗
DOE OSTI2022

Corrosivity Screening of Pyrolysis Bio-Oils by Short-Term Alloy Exposures. Laboratory Analytical Procedure (LAP), Issue Date: May 12, 2022

Bio-oils contain organic acids and oxygenated compounds that can lead to corrosion issues during bio-oil processing and storage. This Laboratory Analytical Procedure (LAP) allows for rapid screening of a bio-oil's corrosivity without the need for complex equipment and long-term exposures. A robust and repeatable method for assessing the corrosivity of bio-oils is necessary in order to remove materials degradation as an obstacle to research, upgrading, use and storage of bio-oils. This LAP involves the incubation of a representative alloy, 410 stainless steel (410 SS), specimen in bio-oil over a period of 48 hours at 50 degrees C in a sealed container. The corrosive species in the bio-oil react with and deplete alloy elements such as iron (Fe) and/or chromium (Cr) from the specimen into the bio-oil solution. The depletion of Fe and Cr from the specimen results in a significant mass loss that can be recorded. The mass loss is directly correlated to the corrosivity of a bio-oil. Examples of bio-oils in scope include the ones produced by fast pyrolysis and catalytic fast pyrolysis, as well as liquids produced from hydrothermal liquefaction.

09 BIOMASS FUELS↗
DOE OSTI2022

MIS Shelf-Life Final Report for Plutonium Oxide Item CAN92 (SSR147) from Rocky Flats Analytical Laboratory Operations

A plutonium/uranium oxide material from the Material Identification and Surveillance (MIS) Program inventory has been studied to determine the gas generation and corrosion behavior in a storage environment. Sample CAN92 represents plutonium/uranium oxides stored in 3013 containers. The material originated in the analytical laboratory at Rocky Flats. This study followed over time the gas pressure and composition of a sample with nominally 0.5 wt% water in a sealed container with an internal volume scaled to 1/400th of the volume of a 3013 container. Gas compositions had been measured periodically over 5 ½ years. The maximum observed gas pressure from gas generation was 117 kPa. The increase over the initial pressure of 77.5 kPa was largely due to the generation of nitrogen and carbon dioxide with minor amounts of hydrogen and nitrous oxide. The internal components of SSR147 were inspected 6.5 years after it was removed from the array. The inside surfaces of the inner bucket exposed to the original sample for 1,937 days had an etched appearance and general corrosion. No pitting was observed on the inner bucket that held the sample.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗