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King, Jeffrey

Publications and source records attributed to King, Jeffrey.

Molecular dynamics simulations of radiation cascade evolution near cellular dislocation structures in additively manufactured stainless steels

The dislocation dense cellular structures observed in additively manufactured (AM) stainless steels can allow these materials to have enhanced strength and ductility compared to conventionally manufactured materials. Effective design of radiation resistant materials often necessitates creating microstructures containing of a high density of dislocations that act as sinks for radiation induced defects. This work uses molecular dynamics simulations to study the impact of pre-existing defects on radiation damage in stainless steel 316L fabricated by the laser powder bed fusion process. The evolution of synthetically generated dislocations in a crystal system in response to multiple radiation collision cascades suggest that dislocation dense regions reduce the probability of surviving point defects forming clusters. This finding seems to result from the dislocation cores’ ability to absorb point defects, thereby limiting the formation of clusters during the recombination phase. However, after successive cascades, the ability of the dislocation entanglement to prevent defect formation is diminished and defect cluster formation trends to an equilibrium. Accordingly, it is hypothesized that in an experimental setting the dislocation cells will initially act as neutral sinks for point defects, potentially delaying the onset of radiation damage effects; but, these structures will be degraded due to radiation-enhanced diffusion and lose their effectiveness at doses above 1.5–2 displacements per atom. Nevertheless, the ability to produce complex and feature-specific microstructures suggests promise for the design of radiation tolerant materials using AM methods.

36 MATERIALS SCIENCE↗

TEM Analysis of Additively Manufactured Stainless Steels Prior to Neutron Irradiation

Austenitic stainless steel (SS-316L) is an extensively researched L-PBF alloy and is widely used as a structural material in light water reactors due to its good creep and fatigue resistance at elevated temperatures. SS-316L’s toughness at low temperature makes it a good candidate to assess the performance of additively manufactured components for nuclear applications. However, component performance is a direct function of environment. A component in a reactor environment is subject to unique challenges in the form of heat and radiation fluxes in comparison to most component applications. Furthermore, the present study seeks to understand the pre- and post-irradiation behavior of L-PBF manufactured SS-316L at the microstructural level.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Optimizing Nuclear Material Accounting and Measurement Systems

The ability to create nuclear weapons from 235 U and 239 Pu makes it imperative to closely account for these materials as they progress through a nuclear fuel cycle. Improved measurement systems provide more accurate estimates of material quantities and material unaccounted for (MUF). This work provides examples of how two safeguards computational toolboxes can optimize and analyze hypothetical nuclear fuel cycle scenarios. The NUclear Measurement System Optimization (NUMSO) toolbox uses operations research techniques to find optimal solutions to safeguards measurement problems based on minimizing the variance of the estimated MUF. The SafeGuards Analysis (SGA) toolbox employs Monte Carlo techniques to analyze a given configuration of measurement methods and material flows to determine the probabilities of Type I (false detection) and Type II (missed detection) errors. Applying these toolboxes to a realistic fuel cycle scenario demonstrates the capability of NUMSO and SGA to address nuclear safeguards problems. Working in tandem, both toolboxes are able to determine how to quickly improve upon an existing safeguards measurement system and to calculate the resulting improvement in the error probabilities of the system. This information shows engineers not only how to develop new measurement systems but also how to improve existing systems in the most efficient manner.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Examining Fuel-Cycle Scenarios with the Safeguards Analysis Toolbox

SafeGuards Analysis (SGA) is a toolbox developed to allow engineers and scientists to create detailed simulations of safeguards material control and accountability simulations. SGA accepts material flow data from an external material flow model, and can be used with any existing fuel cycle or material control code. This work examines some new developments to the SGA code that allow the code to consider material losses over long timeframes. The first scenario described in this paper examined an enrichment facility consisting of two material balance areas (MBAs). Cumulative sum and basic control chart tests evaluate to a case involving a loss of material from both MBAs simultaneously and a case in which material is removed from the facility over a timescale of double the one that the tests were calibrated to detect. A second scenario represents an entire fuel-cycle consisting of four MBAs and two materials of interest (low-enriched uranium and plutonium). This scenario evaluated the calibrated safeguards system with three blind unidentified stream cases, with the goal of determining the calibrated system’s ability to detect where the material loss occurred in each case. SGA was able to produce the expected results for all of the examples examined in this paper, demonstrating that modules produced using the toolbox are capable of examining larger systems in realistic multi-MBA scenarios.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

SafeGuards Analysis

The SafeGuards Analysis (SGA) toolkit is an add-on to existing fuel cycle codes that provides safeguards measurement and evaluation modeling capabilities with associated uncertainty quantification and sensitivity analysis techniques. An important feature of the SGA toolbox is that any other fuel cycle or facility-level code (such as VISION, CYCLUS, et al.) can be easily modified to work with SGA. Thus SGA can incorporate any of the other available fuel cycle codes with minimal modification.

Shugart, Nicolas↗

NUclear Measurement System Optimization

The NUclear Measurement System Optimization (NUMSO) toolbox interfaces with models developed using SGA to provide combined uncertainty and related operations information about the safeguards process. The primary focus of NUMSO is to determine the best locations and operating times for measurement devices to minimize the sum of Type I and Type II errors. A secondary focus is to determine the key contributors to the Type I and Type II errors indicated by SGA. NUMSO can also determine the best devices to recalibrate and the best times to recalibrate those devices given a limited budget.

Johnson, Benjamin↗

A New Modeling Technique to Analyze Safeguards Measurements in Large Systems

SafeGuards Analysis (SGA) is a computational toolbox able to simulate different safeguards scenarios across a number of different fuel cycles and at many different scales within the Matlab Simulink framework. SGA functions by simulating Material Balance Areas (MBAs) under safeguards materials control and accountability and allows the user to define the uncertainty parameters of the associated flow and inventory measurements. The simulated safeguard system uses the uncertain measurement estimates to calculate a mass-balance across the MBA. This mass balance is then evaluated by one of a number of different statistical tests to determine if a significant amount of material has been removed from the MBA. This work describes the design of SGA, the results of testing each element of the toolbox, and a number of single MBA example scenarios. In all of the test cases SGA performed as expected, and produced acceptable results from the single MBA scenario.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Integration Of Launch Vehicle Simulation/Analysis Tools And Lunar Cargo Lander Design

Part 2, which will be discussed in this report, will discuss the development of a Lunar Cargo Lander (unmanned launch vehicle) that will transport usable payload from Trans- Lunar Injection to the moon. The Delta IV-Heavy was originally used to transport the Lunar Cargo Lander to TLI, but other launch vehicles have been studied. In order to uncover how much payload is possible to land on the moon, research was needed in order to design the sub-systems of the spacecraft. The report will discuss and compare the use of a hypergolic and cryogenic system for its main propulsion system. The guidance, navigation, control, telecommunications, thermal, propulsion, structure, mechanisms, landing gear, command, data handling, and electrical power sub-systems were designed by scaling off other flown orbiters and moon landers. Once all data was collected, an excel spreadsheet was created to accurately calculate the usable payload that will land on the moon along with detailed mass and volume estimating relations. As designed, The Lunar Cargo Lander can plant 5,400 lbm of usable payload on the moon using a hypergolic system and 7,400 lbm of usable payload on the moon using a cryogenic system.

DeJean, George Brian↗