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At least 1,675 records · Page 93

Next Generation, Explicitly Correlated Electronic Structure Methods

All common wave function methods of electronic structure theory have a fundamental and troublesome flaw: the inability to correctly describe the exact mathematical cusp behavior of many-electron wave functions in the vicinity of coalescence points (Coulomb singularities), and hence to fully account for instantaneous, short-range correlation among electrons. To achieve high thermochemical accuracy, next-generation methodologies were needed that solve the electron cusp problem by explicitly incorporating interelectronic variables (r 12 ) into molecular wave functions. We pursued a long-term research program to develop practical explicitly-correlated methods, to create attendant, freely available, state-of-the-art computer codes, and to undertake chemical applications of unprecedented size. Our work allows conventional CCSD(T) computations to be conjoined with explicitly-correlated second-order perturbation methods within a focal point extrapolation scheme for pinpointing the ab initio limit of electronic structure theory.

99 GENERAL AND MISCELLANEOUS↗

Demonstrating Reliable High Level Waste Slurry Sampling Techniques to Support Hanford Waste Processing

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HL W) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOC must demonstrate the ability to adequately mix and sample high-level waste feed to meet the WTP Waste Acceptance Criteria and Data Quality Objectives. The sampling method employed must support both TOC and WTP requirements. To facilitate information transfer between the two facilities the mixing and sampling demonstrations are led by the One System Integrated Project Team. The One System team, Waste Feed Delivery Mixing and Sampling Program, has developed a full scale sampling loop to demonstrate sampler capability. This paper discusses the full scale sampling loops ability to meet precision and accuracy requirements, including lessons learned during testing. Results of the testing showed that the Isolok(R) sampler chosen for implementation provides precise, repeatable results. The Isolok(R) sampler accuracy as tested did not meet test success criteria. Review of test data and the test platform following testing by a sampling expert identified several issues regarding the sampler used to provide reference material used to judge the Isolok's accuracy. Recommendations were made to obtain new data to evaluate the sampler's accuracy utilizing a reference sampler that follows good sampling protocol.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Aerosol Formation from High-Pressure Sprays for Supporting the Safety Analysis for the Hanford Waste Treatment and Immobilization Plant

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pretreat and vitrify waste currently stored in underground tanks at Hanford. One of the postulated events in the hazard analysis for the WTP is a breach in process piping that produces a pressurized spray with small droplets that can be transported into ventilation systems. Literature correlations are currently used for estimating the generation rate and size distribution of aerosol droplets in postulated spray releases. These correlations, however, are based on results obtained from small engineered nozzles using Newtonian liquids that do not contain slurry particles and thus do not accurately represent the fluids and breaches in the WTP. A test program was developed to measure the generation rate of droplets suspended in a test chamber and droplet size distribution from a range of prototypic sprays. A novel test method was developed to allow measurement of sprays from small to very large breaches and also includes the effect of aerosol generation from splatter when the spray impacts on walls. Results show that the aerosol generation rate increases with increasing the orifice area, though with a weaker dependence on orifice area than the currently-used correlation. A comparison of water sprays to slurry sprays with 8 to 20 wt% gibbsite or boehmite particles shows that the presence of slurry particles depresses the release fraction compared to water for droplets above 10 μm and increases the release fraction below this droplet size.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

TEM Characterization of High Burn-up Microstructure of U-7Mo Alloy

As an essential part of global nuclear non-proliferation effort, the RERTR program is developing low enriched U-Mo fuels (< 20% U-235) for use in research and test reactors that currently employ highly enriched uranium fuels. One type of fuel being developed is a dispersion fuel plate comprised of U-7Mo particles dispersed in Al alloy matrix. Recent TEM characterizations of the ATR irradiated U-7Mo dispersion fuel plates include the samples with a local fission densities of 4.5, 5.2, 5.6 and 6.3 E+21 fissions/cm3 and irradiation temperatures of 101-136?C. The development of the irradiated microstructure of the U-7Mo fuel particles consists of fission gas bubble superlattice, large gas bubbles, solid fission product precipitates and their association to the large gas bubbles, grain subdivision to tens or hundreds of nanometer size, collapse of bubble superlattice, and amorphisation. This presentation will describe the observed microstructures specifically focusing on the U-7Mo fuel particles. The impact of the observed microstructure on the fuel performance and the comparison of the relevant features with that of the high burn-up UO2 fuels will be discussed.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Computer Modeling of Transport of Oxidizing Species in Grain Boundaries during Zirconium Corrosion

Zirconium (Zr) based alloys are widely used as the cladding materials in light-water reactors. The water-side corrosion of these alloys degrades their structural integrity and poses serious safety concerns. During the Zr corrosion process, a thin Zr oxide (ZrO2) layer forms on the alloy surface and serves as a barrier layer for further corrosion. The majority of the oxide has the monoclinic phase. At the transition region between the oxide and the metal, the oxide contains a thin layer of stabilized tetragonal phase. It is found that the texture of the tetragonal layer determines the protectiveness of the oxide for corrosion. The transport of oxidizing species, such as anion defects, cation defects, and electron through the tetragonal oxide layer could be the rate limiting step of the corrosion. The defect diffusion can be affected by the growing stresses and microstructures such as grain boundaries and dislocations. In this work molecular dynamics simulations are used to investigate the anion and cation diffusion in bulk and at grain boundaries in tetragonal ZrO2. The results show that defect diffusion at grain boundaries is complex and the behavior strongly depends on the grain boundary type. For most of the grain boundaries studied the defect diffusion are much slower than in the bulk, implying that grain boundaries may not be fast defect transport paths during corrosion. The connection between the modeling results and published experimental work will also be discussed. This work is funded by the Laboratory Directed Research and Development (LDRD) program at Idaho National Laboratory.

36 MATERIALS SCIENCE↗

Monitoring and Analysis of In-Pile Phenomena in Advanced Test Reactor using Acoustic Telemetry

The interior of a nuclear reactor presents a particularly harsh and challenging environment for both sensors and telemetry due to high temperatures and high fluxes of energetic and ionizing particles among the radioactive decay products. A number of research programs are developing acoustic-based sensing approach to take advantage of the acoustic transmission properties of reactor cores. Idaho National Laboratory has installed vibroacoustic receivers on and around the Advanced Test Reactor (ATR) containment vessel to take advantage of acoustically telemetered sensors such as thermoacoustic (TAC) transducers. The installation represents the first step in developing an acoustic telemetry infrastructure. This paper presents the theory of TAC, application of installed vibroacoustic receivers in monitoring the in-pile phenomena inside the ATR, and preliminary data processing results.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Open XAL Status Report 2013

XAL is the well established, accelerator physics application programming framework developed for and used at the Spallation Neutron Source in Oak Ridge National Lab. Due to interest from other accelerator labs, the Open XAL project was formed in 2010 to port XAL to be more suitable for collaboration. The Open XAL architecture along with the objectives, status and roadmap of this effort are presented in this paper.

Pelaia, II, Tom↗

EPICS Channel Access Server for LabVIEW

It can be challenging to interface National Instruments LabVIEW (http://www.ni.com/labview/) with EPICS (http://www.aps.anl.gov/epics/). Such interface is required when an instrument control program was developed in LabVIEW but it also has to be part of global control system. This is frequently useful in big accelerator facilities. The Channel Access Server is written in LabVIEW, so it works on any hardware/software platform where LabVIEW is available. It provides full server functionality, so any EPICS client can communicate with it.

Zhukov, Alexander P.↗

A High-Granularity Approach to Modeling Energy Consumption and Savings Potential in the U.S. Residential Building Stock

Building simulations are increasingly used in various applications related to energy efficient buildings. For individual buildings, applications include: design of new buildings, prediction of retrofit savings, ratings, performance path code compliance and qualification for incentives. Beyond individual building applications, larger scale applications (across the stock of buildings at various scales: national, regional and state) include: codes and standards development, utility program design, regional/state planning, and technology assessments. For these sorts of applications, a set of representative buildings are typically simulated to predict performance of the entire population of buildings. Focusing on the U.S. single-family residential building stock, this paper will describe how multiple data sources for building characteristics are combined into a highly-granular database that preserves the important interdependencies of the characteristics. We will present the sampling technique used to generate a representative set of thousands (up to hundreds of thousands) of building models. We will also present results of detailed calibrations against building stock consumption data.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

A REVIEW OF HUMAN-SYSTEM INTERFACE DESIGN ISSUES OBSERVED DURING ANALOG-TO-DIGITAL AND DIGITAL-TO-DIGITAL MIGRATIONS IN U.S. NUCLEAR POWER PLANTS

The United States (U.S.) Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program is developing a scientific basis through targeted research and development (R&D) to support the U.S. nuclear power plant (NPP) fleet in extending their existing licensing period and ensuring their long-term reliability, productivity, safety, and security. Over the last several years, human factors engineering (HFE) professionals at the Idaho National Laboratory (INL) have supported the LWRS Advanced Instrumentation, Information, and Control (II&C) System Technologies pathway across several U.S. commercial NPPs in analog-to-digital migrations (i.e., turbine control systems) and digital-to-digital migrations (i.e., Safety Parameter Display System). These efforts have included in-depth human factors evaluation of proposed human-system interface (HSI) design concepts against established U.S. Nuclear Regulatory Commission (NRC) design guidelines from NUREG-0700, Rev 2 to inform subsequent HSI design prior to transitioning into Verification and Validation. This paper discusses some of the overarching design issues observed from these past HFE evaluations. In addition, this work presents some observed challenges such as common tradeoffs utilities are likely to face when introducing new HSI technologies into NPP hybrid control rooms. The primary purpose of this work is to distill these observed design issues into general HSI design guidance that industry can use in early stages of HSI design.

99 GENERAL AND MISCELLANEOUS↗

NEW AS-RUN NEUTRONICS ANALYSIS FOR RERTR-12 FUEL FOIL EXPERIMENTS

The Reduced Enrichment Research and Test Reactor (RERTR)-12 experiments were designed and carried out in support of what was known as Global Threat Reduction Initiative (GTRI) but has been more recently renamed as Materials Management and Minimization for the Fuel Development (FD) program. From February 2010 through May 2012, the RERTR-12 experimental capsules were inserted into the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for five irradiation cycles. The purpose of these experiments was to “provide comprehensive information on the performance of uranium-molybdenum (U-Mo) based monolithic fuels for research reactor applications.” As-run neutronics, in-cluding depletion, analyses of the experiments have been performed within the Experiment Design and Analysis group at the Idaho National Laboratory. This paper summarizes the results from a new, in-depth as-run analysis that has been recently completed.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Digital Engineering Ecosystem for Innovative Nuclear Technologies

The construction, aerospace, and automotive industries have achieved considerable cost and schedule savings by utilizing virtual design. This program will develop a connected ecosystem of tools to support the design of innovative nuclear technologies. This ecosystem will develop a formal representation of information (data ontology) and systems software to facilitate digital engineering.

42 ENGINEERING↗

Microstructure Characterization and Modeling for Improved Electrode Design

This presentation summarizes fiscal year 2018-2019 work under U.S. Department of Energy's Computer-Aided Engineering of Batteries (CAEBAT) program to develop computational tools for improved electrode design and to provide deeper fundamental understanding of the physics that limit the performance and cause degradation in lithium-ion batteries. Successes include (1) development of an electrode microstructure characterization tool box to be published open source later in 2019, (2) development of a large deformation electrochemical model capturing the volume expansion and performance limits of electrodes utilizing silicon and (3) development of a solid mechanics damage model describing the fracture of polycrystalline nickel-manganese-cobalt cathode materials with cycling.

30 DIRECT ENERGY CONVERSION↗

Demonstrate Thermal Property Measurement on Irradiated Fuel in IMCL

In order to assist in the post-irradiated measurement of thermal conductivity, the Advanced Fuels Campaign (AFC) of the DOE’s Nuclear Technology Research and Development (NTRD) program has invested in the design and build of a thermal conductivity microscope (TCM) system [3] based upon thermoreflectance methods. The TCM was installed into the Thermal Properties Cell (TPC) in the Irradiated Materials Characterization Laboratory at the Idaho National Laboratory’s (INL) Materials and Fuels Complex (MFC) in December 2018. In addition to the TCM, a Netzsch Laser Flash analyzer (LFA) instrument (model LFA427HC) was designed and built via vendor contract and installed into the TPC in April 2019. These instruments were specifically designed for the measurement of thermal conductivity and diffusivity on irradiated fuels and materials. The TPC began radiological operations on September 12, 2019. In order to demonstrate the successful installation of this new measurement capability the U-Zr fuel system, specifically U-10 wt.% Zr, was chosen as the first material to be evaluated due to its importance to the NTRD program. The results of the first four measurements conducted in the TPC on the LFA and the TCM are given in this report.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Global Benefits: the LBNF/DUNE Project

LBNF/DUNE is an international mega-science project hosted by the Department of Energy’s Fermilab. http://www.fnal.gov/dune It will send a beam of tiny particles called neutrinos 1,300 kilometers straight through the earth from Fermilab to the Sanford Underground Research Facility. It will help solve some of the deepest mysteries of the universe and boost innovation while training young people around the world in science, engineering and computing. Scientists and engineers at universities and laboratories are working hand-in-hand with companies to design electronics, build hardware and develop computer programs for the project. LBNF and DUNE will create jobs as well as demand for materials, products and services. Students in dozens of countries around the world will start their careers in science and engineering with this project, and then transfer their knowledge into industry, medicine, computer science and many other fields.

43 PARTICLE ACCELERATORS↗