Publications

Publications

Spontaneous imbibition of water and determination of effective contact angles in the Eagle Ford Shale Formation using neutron imaging

Journal: Spinger Link

Understanding of fundamental processes and prediction of optimal parameters during the horizontal drilling and hydraulic fracturing process results in economically effective improvement of oil and natural gas extraction. Although modern analytical and computational models can capture fracture growth, there is a lack...

The SCALE 6.2 ORIGEN API for High Performance Depletion

In recent years, the SCALE 6.2 development efforts have included modernization of key components of the modular SCALE code system. The ORIGEN depletion/decay module has received extensive improvements, including the addition of an application programming interface (API) for both C++ and Fortran with modern object-...

A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT

Journal: Nuclear Engineering and Technology

An essential component of the neutron transport solver is the resonance self-shielding calculation used to determine equivalence cross sections. The neutron transport code, MPACT, is currently using the subgroup self-shielding method, in which the method of characteristics (MOC) is used to solve purely absorbing fixed...

Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC

Journal: Annals of Nuclear Energy

The MPACT code, being developed collaboratively by the University of Michigan and Oak Ridge National Laboratory, is the primary deterministic neutron transport solver being deployed within the Virtual Environment for Reactor Applications (VERA) as part of the Consortium for Advanced Simulation of Light Water Reactors...

Heat Deposition Analysis for the the High Flux Isotope Reactor's HEU and LEU Core Models

Journal: Nuclear Engineering and Design

The High Flux Isotope Reactor at Oak Ridge National Laboratory is an 85 MWth pressurized light-water-cooled and -moderated flux-trap type research reactor. The reactor is used to conduct numerous experiments, advancing various scientific and engineering disciplines. As part of an ongoing program sponsored by the US...

Supervisory Control System for Multi-Modular Advanced Reactors

The proposed supervisory control system (SCS) may provide considerable benefits to advanced small modular reactors, including reduced plant staffing, optimized maintenance activities, greater plant availability, and higher operating efficiency. The SCS makes risk-informed decisions based on (1) a probabilistic...

Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium

Journal: Annals of Nuclear Energy

Small modular reactors (SMRs) offer potential benefits, such as enhanced operational flexibility. However, it is vital to understand the holistic impact of SMRs on nuclear fuel cycle performance. The focus of this paper is the fuel cycle impacts of light water SMRs in a once-through fuel cycle with low-enriched...

Dynamic Radioisotope Power System Development for Space Explorations

Dynamic power conversion offers the potential to produce radioisotope power systems (RPS) that generate higher power outputs and utilize the Pu-238 radioisotope more efficiently than Radioisotope Thermoelectric Generators (RTG).  Additionally, dynamic systems also offer the potential of producing generators with...

Design of a Universal Canister System for US High-Level Waste

To support the safe clean-up mission of the United States Department of Energy’s Office of Environmental Management (DOE-EM), a concept for a universal canister system for storage, transportation, and eventual disposition of certain high-level waste has been developed.  This concept has been developed to support the...

Overview of Security Considerations for the Back-end of the United States Fuel Cycle

Over 75,000 tons of spent nuclear fuel (SNF) is safely and securely stored at over 70 locations around the United States. Assuring the continued safety, security, and safeguarding of this material must be maintained throughout the life cycle. When the nuclear fuel in a reactor no longer contributes effectively to the...

Summary of Industry Task Orders Completed by the US DOE-NE NFST

The Administration released its Strategy for the Management and Disposal of Used Nuclear Fuel and HighLevel Radioactive Waste in January 20131 . The Strategy includes a phased, adaptive, and consent-based approach to siting, and implementing a comprehensive management and disposal system. These plans include...

U.S. Department of Energy, Office of Nuclear Energy, Nuclear Fuel Storage and Transportation Planning Project Modeling Tools

The U.S. Department Energy, Office of Nuclear Energy’s (DOE-NE) Nuclear Fuels Storage and Transportation (NFST) is developing foundational capabilities and tools to support and inform the future deployment of consolidated interim storage and large-scale transportation of SNF. These tools include Used Nuclear Fuel...

An Evaluation of Standardized Canisters in the Waste Management System

Development of a standardized canister system represents an opportunity to develop an integrated approach to addressing storage, transportation, and disposal issues in the waste management system. However, regardless of timing and method, deployment of such a system would have the potential to cause significant system...

Performance Specifications for Standardized Transportation, Aging, and Disposal Canister Systems

The inventory of commercial spent nuclear fuel (SNF) dry storage is diverse and growing. Utilities are currently loading large canisters with high thermal loads to optimize storage capacity while minimizing cost and operational impacts. These high-capacity canisters may be required to remain in onsite storage for many...

Initial Evaluation of Standardized Canisters in the Waste Management System

Development and deployment of a standardized canister system represents an opportunity to develop an integrated approach to address storage, transportation, and disposal issues in the waste management system. However, this deployment has the potential for significant system-wide impacts regardless of timing and method...

A Review of Multipurpose Canister Concepts for Standardization in the Waste Management System

Since the early 1980s, the federal government and individual utilities have put forth considerable effort to develop a canister for spent nuclear fuel (SNF) that could be used as part of a dry storage system, transportation system, and disposal system without having to be reopened. While the terminology for this type...

Nuclear Fuels Storage and Transportation Planning Project Strategic Crosscutting Activities

The Strategic Crosscut element supports NFST objectives Provides consistent, traceable data and analysis input as well as automated SNF characterization capabilities (UNF-ST&DARDS) Uses current system analysis tools to evaluate different options in the nuclear waste management system, including standardization as...

Dakota Uncertainty Quantification Methods Applied to the CFD Code Nek5000

Predictive modeling and simulation of the performance of a nuclear reactor and its fuel is a challenging task because of the large number of coupled physical phenomena that must be addressed. In addition to this intrinsic complexity, model uncertainty must be accounted for in any analysis if the model will be used to...

In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification

Expanding spent fuel dry storage activities worldwide are increasing demands on safeguards authorities that perform inspections. The European Atomic Energy Community (EURATOM) and the International Atomic Energy Agency (IAEA) require measurements to verify declarations when spent fuel is transferred to difficult-to-...

Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2

Journal: Annals of Nuclear Energy

High quality experimental data for isotopic compositions in irradiated fuel are important to spent fuel applications, including nuclear safeguards, spent fuel storage, transportation, and final disposal. The importance of these data has been increasingly recognized in recent years, particularly as countries like...

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