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Dose Exceedance Distance Sensitivity Based on Parametric Uncertainty

Garcia, Mariah L.; Clavier, Kyle

Sandia National Laboratories (SNL) collaborated with the US Nuclear Regulatory Commission's (NRC) Office of Nuclear Security and Incident Response (NSIR) and Office of Nuclear Regulatory Research (RES) to investigate the reasonable variability in the estimation of dose exceedance distances. SNL performed calculations using the MACCS code to elucidate the sensitivity of dose exceedance distances to variations in user input parameters.

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GDSA Framework Development and Process Model Integration FY2024

Mariner, Paul E.; Leone, Rosemary C.; Debusschere, Bert J.; Madsen, Calvin F.; Curry, Caitlin J.; Garcia, Mariah L.; Prouty, J.L.; Rogers, Ralph; Lopez, Carlos M.; Barela, Amanda C.; Swiler, Laura P.; Harvey, Jacob; Brooks, Dusty M.; Basurto, Eduardo

The Disposal Research & Development (Disposal R&D) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Spent Fuel & High-Level Waste Disposition is conducting research and development (R&D) on geologic disposal of spent nuclear fuel (SNF) and high-level nuclear waste (HLW). A high priority for Disposal R&D is disposal system modeling (Sassani et al. 2023). The Geologic Disposal Safety Assessment (GDSA) work package is charged with developing a disposal system modeling and analysis capability for evaluating generic disposal system performance for nuclear waste in geologic media.

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Use of National Centers for Environmental Prediction (NCEP) Data to Support Severe Accident Consequence Analysis at Locations Without Onsite Meteorological Data

Weiksnar, Kate D.; Garcia, Mariah L.; Nguyen, Audrey T.T.; Clayton, Daniel J.

Certain regulatory actions under 10 CFR Parts 50, 52, or the proposed part 53 require the assessment of the potential off-site consequence risks to public safety and the environment from a hypothetical severe accident. As an important part of these analyses, atmospheric transport and dispersion (ATD) modeling relies heavily on the prevailing weather patterns of a site. When considering future deployment of new reactor designs in areas where historical onsite meteorological data is not available, there exists a need to assess the potential range of severe accident consequences using synthetic weather data. MACCS is designed to estimate consequence measures such as air concentrations, ground depositions, areas under deposition isopleths, radiological doses, and health and economic impacts on an annual-averaged basis by using inputs such as population and site-specific meteorological data. The objective of this work is to investigate the feasibility of supplementing observed site specific weather files with synthetic weather data to calculate these consequence measures. Understanding the probabilistic consequences estimated using synthetic data compared to site-specific observational meteorological data may lead to more agility and flexibility in performing calculation for future situations. This report details the results of research tasks associated with this goal. First, a review was performed to compile a list of potential site-specific meteorological data sources and evaluate their compatibility with MACCS. After selecting a subset of meteorological data, observed and synthetic MACCS weather files were developed for four regions with distinct weather and terrain conditions (Alaskan coastal, large river valley, flat terrain, and gulf coast). Consequence parameters, such as peak time-integrated air and ground concentrations and area under deposition isopleths as a function of distance, were determined for each site and meteorological data set using two distinct source terms. The results demonstrate that use of synthetic meteorological datasets result in consequence values with differences of less than a factor of two from site-specific observational data. The comparisons provided herein can provide decision-makers with additional insight to help evaluate the potential benefit of using national modeled weather data, especially in instances where site specific data over multiple previous years may not be available. The results of these analyses are provided and discussed in this report.

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Assessment of Current MACCS Capabilities for Modeling Atmospheric Physical and Chemical Transformations

Garcia, Mariah L.; Clayton, Daniel J.

The physical and chemical transformation during atmospheric transport of radionuclides released into the environment has the possibility of impacting consequence modeling results. Accordingly, this report identifies physical and chemical transformations that may occur following release of chemically reactive radioactive species, how those transformations may affect modeling of consequences of release to the atmosphere and identifies current capabilities – in both MACCS and other state-of-practice atmospheric transport and dispersions models– to model those transformations. It was found that the inclusion of physical and chemical transformations is currently very limited in current state-of-practice codes for atmospheric dispersion of radionuclides. State-of-practice atmospheric dispersion codes appear to be typically limited to simulating either physical-chemical transformations or radioactive transformations, but not both. A state-of-practice atmospheric dispersion code capable of performing parallel physical, chemical, and radioactive transformation was not identified. A few atmospheric dispersion codes capable of modeling physical and chemical transport of specific species such as tritium or uranium hexafluoride were identified. Consequently, there is currently no information available that clearly suggests updates to the MACCS code are needed to bring it up to state-of-practice. However, investigations concluded that the MACCS computational framework can currently accommodate multiple physical/chemical forms in one simulation. Additionally, with some major assumptions, the computational framework in MACCS can accommodate parallel physical-chemical and radioactive transformations.

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Preparing the MACCS Code for Advanced Reactor Applications

Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, NUTHOS 2024

Garcia, Mariah L.

The MACCS code was created by Sandia National Laboratories for the U.S. Nuclear Regulatory Commission and has been used for emergency planning, level 3 probabilistic risk assessments, consequence analyses and other scientific and regulatory research for over half a century. Specializing in modeling the transport of nuclear material into the environment, MACCS accounts for atmospheric transport and dispersion, wet and dry deposition, probabilistic treatment of meteorology, exposure pathways, varying protective actions for the emergency, intermediate and long-term phases, dosimetry, health effects (including but not limited to population dose, acute radiation injury and increased cancer risk), and economic impacts. Routine updates and recent enhancements to the MACCS code, such as the inclusion of a higher fidelity atmospheric transport and dispersion model, the addition of a new economic impact model, and the application of nearfield modeling, have continuously increased the codes capabilities in consequence analysis. Additionally, investigations of MACCS capabilities for advanced reactor applications have shown that MACCS can provide realistic and informative risk assessments for the new generation of reactor designs. Even so, areas of improvement as well as gaps have been identified that if resolved can increase the usefulness of MACCS in any application regarding a release of nuclear material into the environment.

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Preparing the MACCS Code for Advanced Reactor Applications

Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, NUTHOS 2024

Garcia, Mariah L.

The MACCS code was created by Sandia National Laboratories for the U.S. Nuclear Regulatory Commission and has been used for emergency planning, level 3 probabilistic risk assessments, consequence analyses and other scientific and regulatory research for over half a century. Specializing in modeling the transport of nuclear material into the environment, MACCS accounts for atmospheric transport and dispersion, wet and dry deposition, probabilistic treatment of meteorology, exposure pathways, varying protective actions for the emergency, intermediate and long-term phases, dosimetry, health effects (including but not limited to population dose, acute radiation injury and increased cancer risk), and economic impacts. Routine updates and recent enhancements to the MACCS code, such as the inclusion of a higher fidelity atmospheric transport and dispersion model, the addition of a new economic impact model, and the application of nearfield modeling, have continuously increased the codes capabilities in consequence analysis. Additionally, investigations of MACCS capabilities for advanced reactor applications have shown that MACCS can provide realistic and informative risk assessments for the new generation of reactor designs. Even so, areas of improvement as well as gaps have been identified that if resolved can increase the usefulness of MACCS in any application regarding a release of nuclear material into the environment.

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