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Assess and Benchmark Magneto-Inertial Fusion (MIF) Scaling. Final Technical Report for the SNL/Rochester ALPHA Follow-on Project

Peterson, K.J.

This project was a follow-on to the Sandia National Laboratories (SNL) and the Laboratory for Laser Energetics (LLE) ARPA-E ALPHA project entitled “Demonstrating Fuel Magnetization and Laser Heating Tools for Low-Cost Fusion Energy”. The primary purpose of this follow-on project was to obtain additional data at the OMEGA facility to help better understand how MagLIF, a platform that has already demonstrated the scientific viability of magneto-inertial fusion, scales across a factor of 1000 in driver energy. A secondary aspect of this project was to extend simulations and analysis at SNL to cover a wider magneto-inertial fusion (MIF) parameter space and test scaling of those models across this wide range of input energies and conditions of the target. This work was successful in improving understanding of how key physics elements of MIF scales and improves confidence in setting requirements for fusion gain with larger drivers. The OMEGA experiments at the smaller scale verified the hypothesis that preheating the fuel plays a significant role in introducing wall contaminants that mix into the fuel and significantly degrade fusion performance. This contamination not only impacts target performance but the optimal input conditions for the target. However, analysis at the Z-scale showed that target performance at high preheat levels is limited by the Nernst effect, which advects magnetic flux from the hot spot, reducing magnetic insulation and consequently reduces the temperature of the fuel. The combination of MagLIF experiments at the disparate scales of OMEGA and Z along with a multiscale 3D simulation analysis has led to new insight into the physical mechanisms responsible for limiting target performance and provides important benchmarks to assess target scaling more generally for MIF schemes. Finally, in addition to the MagLIF related work, a semi-analytic model of liner driven Field Reversed Configuration (FRC) was developed that predicts the fusion gain for such systems. This model was also validated with 2D radiation magneto-hydrodynamic simulations and predicts that fusion gains of near unity could be driven by the Z machine.

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TYPE Other Report YEAR 2021
DOIOSTI

MACCS (MELCOR Accident Consequence Code System) User Guide -- Version 4.0

Leute, Jennifer E.; Walton, Fotini; Mitchell, Roger; Eubanks, Lloyd

The MELCOR Accident Consequence Code System (MACCS) is used by Nuclear Regulatory Commission (NRC) and various national and international organizations for probabilistic consequence analysis of nuclear power accidents. This User Guide is intended to assist analysts in understanding the MACCS/WinMACCS model and to provide information regarding the code. This user guide version describes MACCS Version 4.0. Features that have been added to MACCS in subsequent versions are described in separate documentation. This User Guide provides a brief description of the model history, explains how to set up and execute a problem, and informs the user of the definition of various input parameters and any constraints placed on those parameters. This report is part of a series of reports documenting MACCS. Other reports include the MACCS Theory Manual, MACCS Verification Report, Technical Bases for Consequence Analyses Using MACCS, as well as documentation for preprocessor codes including SecPop, MelMACCS, and COMIDA2.

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TYPE SAND Report YEAR 2021
DOIOSTI

Advanced Reactor Safeguards Program Roadmap

Cipiti, Benjamin B.

The Advanced Reactor Safeguards (ARS) program was established in 2020 as part of appropriations for the Advanced Reactor Demonstration Program (ARDP) through the Office of Nuclear Energy in the Department of Energy. The goal of this program is to help address near term challenges that advanced nuclear reactor vendors face in meeting domestic Material Control and Accountancy (MC&A) and Physical Protection System (PPS) requirements for U.S. construction. Existing regulations for safeguards and security, as outlined in the Code of Federal Regulations, were written for large light water reactors, and some of the requirements are not suited to smaller, safer advanced reactor designs. The ARS program seeks to remove roadblocks in the deployment of new and advanced reactors by solving regulatory challenges, reducing safeguards and security costs, and utilizing the latest technologies and approaches for robust plant monitoring and protection. Safeguards and Security by Design (SSBD), or the consideration of safeguards and security requirements early in the design process, is an overarching principle that guides this program. This roadmap discusses the goals of the ARS program, current research, and program plan for the next five years.

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TYPE Other Report YEAR 2021
DOIOSTI

OC6 Phase 1: Investigating the under-prediction of low-frequency hydrodynamic loads and responses of a floating wind turbine

Robertson, Amy; Gueydon, Sebastien; Bachynski, Erin; Wang, Lu; Jonkman, Jason; Alarcon, Daniel; Amet, Ervin; Beardsell, Alec; Bonnet, Paul; Boudet, Bastien; Brun, Cedric; Feron, Marie; Chen, Zheng; Forbush, Dominic D.; Galinos, Christos; Galvan, Joseph; Gilbert, Philippe; Gomez, Juan; Haudin, Florence; Hu, Zhiqiang; Le Dreff, Jean-Baptiste; Leimeister, Mareike; Lemmer, Frank; Li, Haoran; Mckinnon, Gill; Mendikoa, Inigo; Moghtadaei, Abdolmajid; Netzband, Stefan; Oh, Sho; Pegalajar-Jurado, Antonio; Nguyen, Minh Q.; Ruehl, Kelley; Schunemann, Paul; Shi, Wei; Shin, Hyunkyoung; Si, Yulin; Surmout, Florian; Trubat, Pau; Qwist, Jacob; Wohlfahrt-Laymann, Svenja

Abstract not provided.

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TYPE Conference Poster YEAR 2021
OSTI

AlGaN High Electron Mobility Transistor for Power Switches and High Temperature Logic

Klein, Brianna A.; Armstrong, Andrew A.; Allerman, Andrew A.; Nordquist, Christopher D.; Neely, Jason C.; Reza, Shahed; Douglas, Erica A.; Van Heukelom, Michael; Rice, Anthony; Patel, Victor J.; Matins, Benjamin; Fortune, Torben; Rosprim, Mary R.; Caravello, Lisa A.; Bays, Nathan R.; Pipkin, Jennifer R.; Abate, Vincent M.; Kaplar, Robert J.

Abstract not provided.

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TYPE Conference Presentation YEAR 2021
DOIOSTI

Uncertainty Analysis and Software Verification

Leyva, Nha T.A.H.

Uncertainty analyses are an important part of calibrations and testing. They allow researchers insight on how to reduce and mitigate errors in testing. Each device used in testing introduces error in a system, as well as other sources such as environmental conditions, electronics, analog to digital, and random errors. Each source is carefully examined to identify how much error it introduces to a system. These sources are then combined using various methods of uncertainty calculations. To verify and validate software, a manual calculation is required to ensure the software is performing as intended. Using Excel to verify the calculations, we can identify discrepancies within the software. The root of the sum of the squares uncertainty (RSS) is used to find the combined uncertainty of a device at one and two standard deviations of the mean. Calibrations on accelerometers are performed using a vibration system along with a back-toback reference accelerometer. The vibration system takes a reference point at 100Hz frequency at 10g amplitude. The sensitivities are collected at each dialed in frequency. The sensitivity of the device represents the electrical output of the UUT (mV, pC, etc.) per unit of acceleration (g). The full history of sensitivities of selected accelerometers are used to find the averaged, standard deviation, and uncertainty of the device at each frequency tested. The uncertainty calculations from excel and the software are then compared.

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TYPE Other Report YEAR 2021
OSTIDOIOSTI

Salt International Collaborations FY2021 Update

Kuhlman, Kristopher L.; Matteo, Edward N.; Mills, Melissa M.; Jayne, Richard S.; Reedlunn, Benjamin; Sobolik, Steven; Bays, Nathan R.; Stein, Emily; Gross, Mike

This report summarizes the international collaboration work conducted by Sandia and funded by the US Department of Energy Office (DOE) of Nuclear Energy Spent Fuel and Waste Science & Technology (SFWST) as part of the Sandia National Laboratories Salt R&D and Salt International work packages. This report satisfies the level-three milestone M3SF-20SN010303062. Several stand-alone sections make up this summary report, each completed by the participants. The sections discuss international collaborations on geomechanical benchmarking exercises (WEIMOS), granular salt reconsolidation (KOMPASS), engineered barriers (RANGERS), and model comparison (DECOVALEX). Lastly, the report summarizes a newly developed working group on the development of scenarios as part of the performance assessment development process, and the activities related to the Nuclear Energy Agency (NEA) Salt club and the US/German Workshop on Repository Research, Design and Operations.

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TYPE Other Report YEAR 2021
DOIOSTIDOIOSTI

New Geomechanical Computation Analysis Evaluating Behavior of the Fault nearby BC-4

Park, Byoung

BC-4 is an abandoned brining cavern situated in the middle of the site. Its presence poses a concern for several reasons: 1) the cavern was leached up into the caprock; 2) it is similar to BC-7, a brining cavern on the northwest corner of the dome that collapsed in 1954 and now is the home to Cavern Lake; 3) a similar collapse of BC-4 would have catastrophic consequences for the future operation of the site. There exists a previously mapped fault feature in the caprock and thought to extend into the salt dome than runs in close proximity to BC-4. There are uncertainties about the true extent of the fault, and no explicit analysis has been performed to predict the effects of the fault on BC-4 stability. Additional knowledge of the fault and its effects is becoming more crucial as an enhanced monitoring program is developed and installed.

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TYPE Other Report YEAR 2021
DOIDOIOSTIOSTI

Interpolation data transfer between the models before and after a partial drawdown leach in BH

Park, Byoung

It has been recognized that as cavern operations become more frequent due to oil sales, field conditions may arise which require a faster turnaround time of analysis to address potential cavern impacts. This letter describes attempts to implement a strategy of transferring an intermediate solution of a Big Hill (BH) geomechanical model from a previous finite element mesh with a specified cavern geometry, to a new mesh with a new cavern geometry created by leaching from an oil sale operation.

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TYPE Other Report YEAR 2021
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Results 13201–13400 of 101,000
Results 13201–13400 of 101,000
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