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At least 1,513 records · Page 84

The Capability Portfolio Analysis Tool (CPAT): A Mixed Integer Linear Programming Formulation for Fleet Modernization Analysis (Version 2.0.2).

In order to effectively plan the management and modernization of their large and diverse fleets of vehicles, Program Executive Office Ground Combat Systems (PEO GCS) and Program Executive Office Combat Support and Combat Service Support (PEO CS&CSS) commis- sioned the development of a large-scale portfolio planning optimization tool. This software, the Capability Portfolio Analysis Tool (CPAT), creates a detailed schedule that optimally prioritizes the modernization or replacement of vehicles within the fleet - respecting numerous business rules associated with fleet structure, budgets, industrial base, research and testing, etc., while maximizing overall fleet performance through time. This paper contains a thor- ough documentation of the terminology, parameters, variables, and constraints that comprise the fleet management mixed integer linear programming (MILP) mathematical formulation. This paper, which is an update to the original CPAT formulation document published in 2015 (SAND2015-3487), covers the formulation of important new CPAT features.

97 MATHEMATICS AND COMPUTING↗

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Accident Tolerant Fuels High Impact Problem: FeCrAl Modeling Capabilities

Iron-chromium-aluminum alloys are a potential candidate replacement for zirconium-based claddings in light water reactor fuel rods due to their increased strength (lower creep rates and higher yield stress) and slower oxidation kinetics with steam. Their larger neutron absorption cross-section necessitates thinner claddings and larger fuel pellets to maintain the same as-fabricated fuel-to-clad gap. The aggressive development schedule of the United States Department of Energy's (DOE) Advanced Fuels Campaign (AFC) to have potential accident tolerant fuels (ATF) concepts in lead test rods or assemblies by 2022 has necessitated the need for advanced modeling and simulation techniques to investigate the behavior of these materials under normal operating and accident conditions. This report presents the modeling capabilities for FeCrAl claddings at the engineering (continuum) scale developed as part of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) high impact problem (HIP). Sensitivity studies of select material parameters have been completed to determine their significance in predictions of important fuel performance parameters such as fuel centerline and surface temperatures, cladding stresses and strains, fission gas released, and rod internal pressure. Comparative analyses of FeCrAl and Zircaloy-4 claddings for separate effects conditions are presented.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

The Proliferation of Unmanned Aerial Vehicles: Terrorist Use, Capability, and Strategic Implications

There has been unparalleled proliferation and technological advancement of consumer unmanned aerial vehicles (UAVs) across the globe in the past several years. As witnessed over the course of insurgency tactics, it is difficult to restrict terrorists from using widely available technology they perceive as advantageous to their overall strategy. Through a review of the characteristics, consumer market landscape, tactics, and countertactics, as well as operational use of consumer-grade UAVs, this open-source report seeks to provide an introductory understanding of the terrorist-UAV landscape, as well as insights into present and future capabilities. The caveat is evaluating a developing technology haphazardly used by terrorists in asymmetric conflicts.

42 ENGINEERING↗

Multi-phase model development to assess RCIC system capabilities under severe accident conditions

The Reactor Core Isolation Cooling (RCIC) System is a safety-related system that provides makeup water for core cooling of some Boiling Water Reactors (BWRs) with a Mark I containment. The RCIC System consists of a steam-driven Terry turbine that powers a centrifugal, multi-stage pump for providing water to the reactor pressure vessel. The Fukushima Dai-ichi accidents demonstrated that the RCIC System can play an important role under accident conditions in removing core decay heat. The unexpectedly sustained, good performance of the RCIC System in the Fukushima reactor demonstrates, firstly, that its capabilities are not well understood, and secondly, that the system has high potential for extended core cooling in accident scenarios. Better understanding and analysis tools would allow for more options to cope with a severe accident situation and to reduce the consequences. The objectives of this project were to develop physics-based models of the RCIC System, incorporate them into a multi-phase code and validate the models. This Final Technical Report details the progress throughout the project duration and the accomplishments.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Advance High Temperature Inspection Capabilities for Small Modular Reactors: Part 1 - Ultrasonics

The project objective was to investigate the development non-destructive evaluation techniques for advanced small modular reactors (aSMR), where the research sought to provide key enabling inspection technologies needed to support the design and maintenance of reactor component performance. The project tasks for the development of inspection techniques to be applied to small modular reactor are being addressed through two related activities. The first is focused on high temperature ultrasonic transducers development (this report Part 1) and the second is focused on an advanced eddy current inspection capability (Part 2). For both inspection techniques the primary aim is to develop in-service inspection techniques that can be carried out under standby condition in a fast reactor at a temperature of approximately 250°C in the presence of liquid sodium. The piezoelectric material and the bonding between layers have been recognized as key factors fundamental for development of robust ultrasonic transducers. Dielectric constant characterization of bismuth scantanate-lead titanate ((1-x)BiScO 3 -xPbTiO 3 ) (BS-PT) has shown a high Curie temperature in excess of 450°C , suitable for hot stand-by inspection in liquid metal reactors. High temperature pulse-echo contact measurements have been performed with BS-PT bonded to 12.5 mm thick 1018-low carbon steel plate from 20C up to 260 C. High temperature air-backed immersion transducers have been developed with BS-PT, high temperature epoxy and quarter wavlength nickel plate, needed for wetting ability in liquid sodium. Ultrasonic immersion measurements have been performed in water up to 92C and in silicone oil up to 140C. Physics based models have been validated with room temperature experimental data with benchmark artifical defects.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Progress Towards an Indirect Neutron Capture Capability at LANSCE: October 2017 – March 2018

We describe progress developing the Device for Indirect Capture Experiments on Radionuclides (DICER) on flight path 13 at the Lujan Center at the Los Alamos Neutron Science Center (LANSCE). This capability is being developed to tightly constrain neutron-capture cross section on short-lived radioactive nuclides of high importance to weapons-program sponsors via neutron total cross section measurements on the same nuclides. In this report, we describe progress in this endeavor during October 2017 through March 2018.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

ECP ST Capability Assesment Report VTK-m

The ECP/VTK-m project is providing the core capabilities to perform scientific visualization on exascale architectures. The ECP/VTK-m project fills the critical feature gap of performing visualization and analysis on processors like graphics-based processors and many integrated core. The results of this project will be delivered in tools like Para View, Vislt, and Ascent as well as in stand-alone form. Moreover, these projects are depending on this ECP effort to be able to make effective use of ECP architectures.

97 MATHEMATICS AND COMPUTING↗

Non-algorithmic Capability Gaps for CYCLUS and CYCAMORE Transition Analyses

As part of NEUP-FY16-10512, fuel cycle transition scenarios were simulated using CYCLUS and existing CYCAMORE archetypes. The purpose of this paper is to identify current non-algorithmic gaps in the capabilities necessary for key transition scenarios. The gaps identified through this exercise mainly pertain to the greedy exchange model, and the manual, static parameter of fuel cycle facilities. The scenarios are from the Idaho National Laboratory Nuclear Fuel Cycle Evaluation and Screening Report (Hereby E&S Report). The transition scenarios begin with EG01 and transition to EG23, EG24, EG29, EG30, separately.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Establishing New Capability of High Temperature Electrochemical Impedance Spectroscopy Techniques for Equilibrium and Kinetic Experiments

In nuclear fuel and cladding materials, changes in structure and chemistry over the lifetime of the fuel can have a significant impact on fuel and reactor performance. Currently, chemical evolution over the lifetime of the fuel can only be inferred using post-irradiation examination. As an alternative to post-irradiation measurements, electrochemical impedance spectroscopy (EIS) can provide an in-pile measurement of changes in chemistry in oxides and hydrides coupling with modeling such as finite element (FE) and other material characterization techniques such as atom probe tomography (APT), Raman spectroscopy, in-situ Transmission Electron Microscopy (TEM), and synchrotron X-ray microscopy. The objective of this work package is to develop EIS techniques for the in-pile measurement of changes in solid state chemistry of fuels and materials in coupling with model simulation and material characterization. This work package will involve the initial development of electrochemical sensing technologies for measuring spatial- and time-resolved changes in fuel and cladding chemistry. Specific attention will be paid to monitoring changes in fuel stoichiometry, monitor cladding hydride formation and deformation, and cladding corrosion. This report summarized the FY17 achievements of this work package. A laboratory was begun to set up from scratch. The laboratory place was located; necessary equipment and materials were purchased and some were delivered; laboratory instruction (LI) for conducting experiments was drafted for review; radiation level of depleted UO2 that will be investigated as the potential testing sample was valued for safety issue; a testing plan for measuring changes in stoichiometry of oxide fuels has been made and roadblocks for making measurements at high temperature have been pinpointed; in addition, collaboration with Boise State University (BSU) and Massachusetts Institute of Technology (MIT) has been established. In short, the capability of applying EIS for in-pile measurement of changes of fuels and cladding materials was initiated to be established.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Progress Towards an Indirect Neutron Capture Capability at LANSCE: October 2017 – September 2018

We describe progress developing the Device for Indirect Capture Experiments on Radionuclides (DICER) on flight path 13 at the Lujan Center at the Los Alamos Neutron Science Center (LANSCE). This capability is being developed to tightly constrain neutron-capture cross section on short-lived radioactive nuclides of high importance to weapons-program sponsors via neutron total cross section measurements on the same nuclides. In this report, we describe progress in this endeavor during October 2017 through September 2018.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Development of an Active, Man-Portable, Cooling System with Dehumidification Capabilities for Personal Protective Clothing/Equipment

Mainstream Engineering Corporation completed a highly successful SBIR program, during which we developed and commercialized products for microclimate cooling systems (MCS) and the heating, ventilation, air-conditioning, and refrigeration (HVAC/R) industry. We are marketing the MCS family of products for use with personal protective clothing/equipment (PPC/PPE) for firefighters, workers in clean rooms, HAZMAT response and other contamination/remediation teams, and military personnel that are required to wear Mission-Oriented Protective Posture (MOPP) suits and bomb disposal suits. Workers in these industries risk heat stress when confined within protective garments while in hot and humid environments. Our family of MCS and HVAC/R products that resulted from this SBIR program includes: 1. Active, Man-Portable, MCS for PPC/E—Our active system provides 350 W cooling of personal cooling for workers in thermally stressed environments. Although industrially hardened, this system is compact (0.69 ft 3 ) and lightweight (22.9 lbs). The MSC is easily decontaminated or disposed of between uses. 2. Miniature Screw Compressor for MCS—Our 350 Wcooling miniature screw compressor was originally designed for MCS and personal cooling systems. Occupying only 11 in 3 and weighing 1.4 lbs, the size and weight are less than any commercially available compressor with a similar cooling capacity. This miniature screw compressor is marketable as a low-pressure compressor or refrigerant pump. 3. Miniature Sliding Vane Compressor and Drive for MCS—Our 350 Wcooling compressor subassembly consists of a commercial miniature sliding vane compressor packaged with our motor controller. At 29.4 in3 and 1.5 lbs, this compressor is larger and heavier than the miniature screw but is lower cost and capable of producing higher head pressure. 4. Small Screw Compressor for HVAC/R—Our 50 kW cooling small screw compressor is for commercial HVAC/R applications. This compressor is extremely power dense at 0.34 ft 3 and 43 lbs and has a specific cooling capacity (kW/lb) five times greater than existing commercial compressors. We demonstrated high reliability (>5,100 hrs of operation and >3,400 on/off cycles), and we are currently discussing commercialization opportunities with laser manufacturers for cooling of their high-power devices. This final report summarizes the design, fabrication, testing, features, and benefits of each product. The commercialization potential and recommendations for the future are included.

42 ENGINEERING↗

Relativistic Modeling Capabilities in Perseus Extended MHD Simulation Code for HED Plasmas

This project is submitted in response to DE-FOA-0001153, and will be carried out by Dr. Charles Seyler and Dr. Nathaniel Hamlin as post doc under the direction of Professor Seyler. The objectives are to enable PERSEUS to self-consistently model relativistic high-energy-density (HED) laboratory and astrophysical phenomena. Electrons and ions in a plasma are generally modeled either as fluids using a two-fluid code, like PERSEUS, or as particles using a Particle-In- Cell (PIC) code. Nonrelativistic PERSEUS solves the two-fluid equations, formulated in terms of a generalized Ohm’s law (GOL), so as to model about nine orders of magnitude in density variation using a local semi-implicit method. Relativistic PERSEUS preserves this structure and therefore retains these advantageous properties, enabling it to model a broader range of relativistic HED phenomena than previous codes. We have also overcome a major technical challenge associated with solving a relativistic system of equations relating conserved quantities (momentum, energy, etc.) to primitive variables (density, velocity, and pressure). We have thus far developed a relativistic version of PERSEUS and demonstrated that it recovers expected nonrelativistic results. We are currently using relativistic PERSEUS to model two HED phenomena, namely laser-plasma interactions and X-pinches, both of which show spectroscopic evidence of relativistic electrons. In an X-pinch, a section of wire carrying sufficiently large current forms a plasma column that pinches down to a point-like source, generating X-rays for use in radiographic imaging. Laser-plasma interactions have been simulated using PIC codes, and we use their results as a benchmark for comparison. However, neither PIC codes nor existing two-fluid schemes can simulate X-pinches, due to the broad range of densities which have thus far made such a simulation computationally prohibitive. In both laser-plasma interaction and Xpinch simulations, we have observed relativistic phenomena that PERSEUS could not previously model. This includes relativistic channeling of a laser into an over-dense deuterium gas (i.e. induced transparency), consistent with PIC simulation results, along with energetic electrons and ions following an X-pinch and likely accompanied by strong X-ray emission, consistent with experimental observations of energetic X-rays. This proposal includes our latest simulation results. We will improve computational efficiency with techniques that allow the use of a less refined numerical grid. This will enable extensions to three-dimensional geometries. We will improve modeling of laser-plasma interactions and X-pinches, including radiative transport processes, in order to improve comparisons with PIC simulations and experimental diagnostics. We will also model power loss through electrode surface plasmas in magnetically insulated transmission lines (MITLs). We will model relativistic astrophysical phenomena in both astrophysical and HED regimes, which could shed light on the validity of laboratory astrophysics for certain problems. These phenomena are currently modeled using PIC codes and existing relativistic two-fluid codes, neither of which can model the range of length scales of which relativistic PERSEUS is capable. There is strong potential for this project to have a broad impact on both the astrophysical and laboratory plasma communities. In the laboratory community, our work is applicable to those concerned with laser-plasma interactions such as laser-driven fusion, and those in the dense Z pinch community concerned with X-pinches and electrode surface plasmas. An improved understanding of the mechanisms of hard (i.e. high-energy) X-ray generation will likely make important contributions toward the use of X-pinches for radiography through the harnessing or mitigation of hard X-rays, depending on the application. The modeling of electrode surface plasmas, including vacuum electron flow, will improve our understanding of power loss to various loads.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

1.5D BISON simulation capability CASL FY17 letter report

This milestone report documents the recently developed 1.5D capability in BISON. As the application of BISON expands the design requirements evolve. The initial emphasis of BISON development focused on multi-dimensional/multi- physics fuel performance simulation. The CASL program has demonstrated the need for a fast running, simplified version of BISON for use in large multi-physics simulations involving hundreds for individual fuel rods in VERA. This document shows the progress to date, and identifies needs for future development.

97 MATHEMATICS AND COMPUTING↗

A survey of additive manufacturing capabilities

A previous ORNL report [1] focused on early AM material considerations for reactor technologies and provided some initial licensing considerations. The current report is a complement to the previous report, providing a survey of AM capabilities that could be used to manufacture SPR SSCs. Specific reactor use cases and overviews of various reactor types are not included in this report.

36 MATERIALS SCIENCE↗

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Accident Tolerant Fuels High Impact Problem: U 3 Si 2 Modeling Capabilities

U 3 Si 2 fuel is a potential candidate replacement for UO 2 in light water reactor fuel rods due to its higher uranium density and thermal conductivity. Its lower melting temperature and significant gaseous swelling may be of concern. The aggressive development schedule of the United States Department of Energy’s (DOE) Advanced Fuels Campaign (AFC) to have potential accident tolerant fuels (ATF) concepts in lead test rods or assemblies by 2022 has necessitated the need for advanced modeling and simulation techniques to investigate the behavior of these materials under normal operating and accident conditions. This report presents the modeling capabilities for U 3 Si 2 fuel at the engineering (continuum) scale developed as part of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) high impact problem (HIP). In this report, the models incorporated into the BISON fuel for U 3 Si 2 are described and comparisons to conventional UO 2 for separate effects cases are presented.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

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↗

ECP ST Capability Assesment Report (CAR) for VTK-m (FY18)

The ECP/VTK-m project is providing the core capabilities to perform scientific visualization on Exascale architectures. The ECP/VTK-m project fills the critical feature gap of performing visualization and analysis on processors like graphics-based processors and many integrated core. The results of this project will be delivered in tools like ParaView, Vislt, and Ascent as well as in stand-alone form. Moreover, these projects are depending on this ECP effort to be able to make effective use of ECP architectures.

97 MATHEMATICS AND COMPUTING↗