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At least 109 records · Page 6

PNNL Biodiversity Library Plugin

The PNNL Biodiversity Plugin is a software tool for Skyline and is designed to allow pathway-centric browsing of peptides previously identified by LC-MS/MS. The plugin is designed to assist in SRM assay design or DIA data analysis. Users select an organism and biological pathway of interest, then the plugin shows information about the associated peptides.

Wilkins, Christopher↗

Leaf gas exchange (BNL-PNNL collaboration), San Lorenzo, Panama, 2020

This data package contains Photosynthetic CO2 response (ACi curves) and Light Response (AQ) of mature sunlit canopy leaves of 11 species from PA-SLZ, February 2020. Branches were cut from the top of the canopy and re-cut under water. Fitted Vcmax and Jmax photosynthetic parameters were derived from measured data as well as the convexity, light use efficiency and apparent quantum yield. This data was collected as a collaboration between Brookhaven National Laboratory (BNL) and Pacific Northwest National Laboratory (PNNL), and is a subset of the 2020 BNL Panama campaign. The species included in this dataset are: Apeiba membranacea, Carapa guianensis, Cespedesia spathulate, Jacaranda copaia, Lonchocarpus heptaphyllus, Pera arboea, Pourouma bicolore, Symphonia globulifera, Tachigali versicolor, Tapirira guianensis, and Virola sebifera. The files included in this data package are in .csv and .pdf format, with two Excel files containing additional metadata.

54 ENVIRONMENTAL SCIENCES↗

Sigma Team for Minor Actinide Separation: PNNL FY 2011 Status Report

This report summarizes work conducted in FY 2011 at PNNL to investigate new methods of separating the minor actinide elements (Am and Cm) from the trivalent lanthanide elements, and separation of Am from Cm. For the former, work focused on a solvent extraction system combining an acidic extractant (HDEHP) with a neutral extractant (CMPO) to form a hybrid solvent extraction system referred to as TRUSPEAK (combining the TRUEX and TALSPEAK processes). For the latter, ligands that strongly bing uranyl ion were investigated for stabilizing corresponding americyl ion.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

EMP Attachment 1: DOE-SC PNNL Site Sampling and Analysis Plan

This Sampling and Analysis Plan (SAP) is written for the radiological environmental air surveillance program for the DOE-SC PNNL Site, Richland Washington. It provides the requirements for planning sampling events, and the requirements imposed on the analytical laboratory analyzing the air samples. The actual air sampling process is in procedure EPRP-AIR-029. The rationale for analyte selection, media, and sampling site location has been vetted through the data quality objectives (DQO) process (Barnett et al. 2010). The results from the DQO process have been reviewed and approved by the Washington State Department of Health. The DQO process (Barnett et al. 2010) identified seven specific radionuclides for analysis along with the need for gross alpha and gross beta radiological analyses. The analytes are 241<\sup>Am, 243<\sup>Am, 244<\sup>Cm, 60<\sup>Co, 238<\sup>Pu, 239<\sup>Pu, and 233<\sup>U. The report also determined that air samples for particulates are the only sample matrix required for the monitoring program. These samples are collected on 47-mm glass-fiber filters.

54 ENVIRONMENTAL SCIENCES↗

User Guide for the STAYSL PNNL Suite of Software Tools

The STAYSL PNNL software suite provides a set of tools for working with neutron activation rates measured in a nuclear fission reactor, an accelerator-based neutron source, or any neutron field to determine the neutron flux spectrum through a generalized least-squares approach. This process is referred to as neutron spectral adjustment since the preferred approach is to use measured data to adjust neutron spectra provided by neutron physics calculations. The input data consist of the reaction rates based on measured activities, an initial estimate of the neutron flux spectrum, neutron activation cross sections and their associated uncertainties (covariances), and relevant correction factors. The output consists of the adjusted neutron flux spectrum and associated covariance matrix, which is useful for neutron dosimetry and radiation damage calculations.

Reactor dosimetry, neutron spectral adjustment↗

Summary of the Graduate Mentoring Assistance Program for PNNL PNNL.12.006 (April 2012 – May 31, 2013)

Summary of Students and Projects: Sarah Bender: The possible improvement of the Multi-Isotope Process (MIP) Monitor by the addition of Compton suppression is investigated for this study. The Compton continuum from the dominant 661.7 keV Cs-137 fission product peak obscures lower energy lines which could be used for spectral and multivariate analysis. A novel Compton suppression system which uses fast, room-temperature materials will be developed using simulation. As opposed to the standard high purity germanium (HPGe) detector suppressed using a thallium-doped sodium iodide (NaI(Tl)) guard detector array, cerium-doped lanthanum bromide (LaBr3) will be used as the primary spectroscopic detector. For Sarah’s Master’s degree, she constructed and validated the unsuppressed detector response of the Pennsylvania State University (PSU)-Compton suppression system. For Sarah’s PhD, she is completing that simulation by including the suppressed operation which will be validated with spent fuel samples. She is also going to use the validation of suppressed operation to predict the detector response of a LaBr3 based Compton suppression system. Richard Clark: Richard Clark completed his study this FY of a new technique known as Intrinsic Dosimetry. Intrinsic Dosimetry is the method of measuring total absorbed dose received by the walls of a container holding radioactive material. By considering the total absorbed dose received by a container in tandem with the physical characteristics of the radioactive material housed within that container, this method has the potential to provide enhanced pathway information regarding the history of the container and its radioactive contents. The latest in a series of experiments designed to validate and demonstrate this newly developed tool are reported. Kenneth Dayman: The MIP Monitor is an online, non-destructive approach to process monitoring in a nuclear fuel reprocessing facility using gamma spectra taken of process streams and multivariate data analysis to detect anomalies in operation. Last year, Mr. Dayman investigated methods to classify spent nuclear fuel according to both reactor type and burn up based on the constituent nuclide activities, which may be used to more accurately calibrate other models in an analysis scheme in order to improve the accuracy and precision of predictions. He is currently writing up his results for publication and has transitioned to another project with Dr. Derrick Haas at PNNL.

Schwantes, Jon M.↗

INL Assessment of PNNL Water Conservation Study for the ATR Complex

To support the implementation of the U.S. Department of Energy (DOE) Strategic Sustainability Performance Plan (SSPP), the DOE Sustainability Performance Office (SPO) sponsored three comprehensive water assessments performed by Pacific Northwest National Laboratory (PNNL) in their 2012 report. As DOE’s third largest water user, Idaho National Laboratory (INL) was one of the selected assessment sites.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

Nuclear Fuel Cycle Reasoner: PNNL FY12 Report

Building on previous internal investments and leveraging ongoing advancements in semantic technologies, PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In developing this proof of concept prototype, the utility and relevancy of semantic technologies to the Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D) has been better understood.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Nuclear Fuel Cycle Reasoner: PNNL FY13 Report

In Fiscal Year 2012 (FY12) PNNL implemented a formal reasoning framework and applied it to a specific challenge in nuclear nonproliferation. The Semantic Nonproliferation Analysis Platform (SNAP) was developed as a preliminary graphical user interface to demonstrate the potential power of the underlying semantic technologies to analyze and explore facts and relationships relating to the nuclear fuel cycle (NFC). In Fiscal Year 2013 (FY13) the SNAP demonstration was enhanced with respect to query and navigation usability issues.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

CAS-NETL-PNNL CEP Program Final Report

This collaborative joint research project is in the area of advanced gasification and conversion, within the CAS-NETL-PNNL Memorandum of Understanding. The goal is the development and testing of an integrated warm syngas cleanup process. This effort is focused on an advanced, integrated system for capture and removal of alkali, sulfur, PH3, AsH3, chloride, and CO2, leading to a future process demonstration at a CAS gasification facility. Syngas produced by gasification can be used for production of fuels (Fischer-Tropsch, SNG, mixed alcohols), chemicals (MeOH, NH3), and hydrogen for fuel cells and IGCC. To employ this syngas, especially for synthesis reactions, contained impurities must be removed to sub-ppmv levels [1]. Commercially available approaches to remove contaminant species suffer from inefficiencies, employing solvents at ambient or lower temperature along with backup sacrificial sorbents, whereas syngas utilization occurs at higher temperatures. The efficiency and economics syngas utilization can be significantly improved if all the contaminants and CO2 are removed at temperatures higher than the chemical synthesis reaction temperatures (> 250 °C) [2].

alkali↗

Evaluation of Low-E Storm Windows in the PNNL Lab Homes

This study examines the performance of exterior and interior low-e storm panels with a controlled whole home experimental design using PNNL's Lab Homes. Summing the estimated annual average heating and cooling savings, the installation of low-e storm panels resulted in approximately 10% annual energy savings. The results of the experiment will be used to determine and validate performance of low-e storm windows over double pane clear glass windows in a whole home setting.

energy savings↗

Establishment of a Background Environmental Monitoring Station for the PNNL Campus

The environmental surveillance of background levels of radionuclides and, in particular, the siting of a background environmental surveillance (monitoring) station are examined. Many published works identify and stress the need for background monitoring; however, little definitive and comprehensive information for siting a station exists. A definition of an ideal background monitoring location and the generic criteria recommended for use in establishing such a background monitoring location are proposed. There are seven primary (mandatory) criteria described with two additional, optional criteria. The criteria are applied to the Richland, Washington (WA), Pacific Northwest National Laboratory (PNNL) Campus, which currently uses background monitoring data from the nearby Hanford Site. Eleven potential background monitoring sites were identified, with one location in Benton City, WA found to meet all of the mandatory and optional criteria. It is expected that the new sampler will be installed and operating by the end of June, 2015.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Final Report: SECA Core Technology Program - PNNL

This report summarizes results from experimental and modeling studies performed by researchers at Pacific Northwest National Laboratory on behalf of the Solid-State Energy Conversion Alliance (SECA) Core Technology Program. The work was performed from 1999 through 2014, under FWP 40552. PNNL’s scientific and technical contributions included development/evaluation of improved materials and fabrication processes for solid oxide fuel cell (SOFC) components, development/implementation of modeling tools to facilitate cell and stack design and optimization, and improved understanding/mitigation of SOFC performance degradation mechanisms. Primary areas of contribution were 1) Materials and fabrication processes, 2) Modeling and simulation tools, 3) Understanding of degradation mechanisms, and 4) New test protocols. The report contains brief descriptions of primary scientific and technical achievements; references to detailed descriptions of the work (patents, papers, and reports) are also provided.

30 DIRECT ENERGY CONVERSION↗

Absorber Column CFD model validation against PNNL’s device-scale absorber column on the LCFS unit

Absorber column has been widely used for CO 2 capture in the coal-fired power plants. High-fidelity CFD models play an important role in absorber column design and solvents optimization, which help enhance the CO 2 capture efficiency and reduce the operation cost. This report provides a comprehensive description of the development of CFD absorber models at two different levels, the design and implementation of PNNL’s device-scale absorber column experiment, and the methodology to combine the CFD results, experiment data, and Aspen model for a better understanding of the interface area in packed column. A composite model is firstly proposed in the Discrete Element Method (DEM) packing process, which can model the complex geometry of various packing elements. This generates a realistic packing pattern and accurate packing porosity ε and specific area a p compared to the actual values for absorber column used in LCFS. Two level of CFD absorber models were developed, namely the full-size column model (FCM) to simulate the entire packed column with a focus on the wall/entrance effects, and the representative column model (RCM) to simulate a section of column with a focus on the sensitivity study of interface area. A Design of Experiment (DoE) plan was developed to guide the collection of 100 run CFD data and 12 experiment runs. The 100 CFD runs were carried out in the RCM with Pro-Pak packing and cover a wide operation range and solvent properties. Impact of influential factors on the interface area in packed column were investigated in details. The CFD interface area was then combined with the experimental data and Aspen model to infer some information of the effective contact angle in the column. The accuracy and uncertainties in the interface area and contact angle can be quantified.

01 COAL, LIGNITE, AND PEAT↗

Furthering Advancements to Shorten the Time (FAST) to Commissioning for Pumped Storage Hydropower (PSH) Prize (Penn State-PNNL): Cooperative Research and Development Final Report, CRADA Number CRD-19-00842

The National Renewable Energy Laboratory (NREL) initiated a Prize with support from Argonne National Laboratory (ANL), Oak Ridge National Laboratory (ORNL), and Pacific Northwest National Laboratory (PNNL), and sponsored by the U.S. Department of Energy Water Power Technologies Office (DOE WPTO) to encourage ideas to reduce the time to commissioning for PSH projects. As a result, nine finalists have been chosen to develop their concepts in advance of the FAST Prize Pitch Contest to be held on October 7, 2019. The national labs will provide technical and business advisement to the noted FAST Prize finalists in preparation for this Pitch Contest.

13 HYDRO ENERGY↗