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-...

Multigroup Monte Carlo on GPUs: Comparison of history- and event-based algorithms

Journal: Annals of Nuclear Energy

This paper presents an investigation of the performance of different multigroup Monte Carlo transport algorithms on GPUs with a discussion of both history-based and event-based approaches. Several algorithmic improvements are introduced for both approaches. By modifying the history-based algorithm that is...

Advancing the Fork detector for quantitative spent nuclear fuel verification

Journal: Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

The Fork detector is widely used by the safeguards inspectorate of the European Atomic Energy Community (EURATOM) and the International Atomic Energy Agency (IAEA) to verify spent nuclear fuel. Fork measurements are routinely performed for safeguards prior to dry storage cask loading. Additionally, spent fuel...

Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines

Journal: Nuclear Science and Engineering

In this paper, three complementary methods have been implemented in the code Denovo that accelerate neutral particle transport calculations with methods that use leadership-class computers fully and effectively: a multigroup block (MG) Krylov solver, a Rayleigh quotient iteration (RQI) eigenvalue solver, and a...

A Novel Technique Applying Spectral Estimation to Johnson Noise Thermometry

Journal: Nuclear Technology

Johnson noise thermometry is one of many important measurement techniques used to monitor the safety levels and stability in a nuclear reactor. However, this measurement is very dependent on the minimal electromagnetic environment. Properly removing unwanted electromagnetic interference (EMI) is critical for accurate...

High burn-up spent nuclear fuel transport reliability investigation

Journal: Nuclear Engineering and Design

Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During road or rail transportation, SNF will experience unique conditions that could affect the structural integrity of the cladding due to vibrational and impact...

High-temperature effects on the light transmission through sapphire optical fiber

Journal: Journal of the American Ceramic Society

Single crystal sapphire optical fiber was tested at high temperatures (1500°C) to determine its suitability for optical instrumentation in high‐temperature environments. Broadband light transmission (450‐2300 nm) through sapphire fiber was measured as a function of temperature as a test of the fiber's ability to...

Nuclide depletion capabilities in the Shift Monte Carlo code

Journal: Annals of Nuclear Energy

A new depletion capability has been developed in the Exnihilo radiation transport code suite. This capability enables massively parallel domain-decomposed coupling between the Shift continuous-energy Monte Carlo solver and the nuclide depletion solvers in ORIGEN to perform high-performance Monte Carlo depletion...

ORNL: Providing access to nuclear infrastructure, expertise

Journal: Nuclear News

The Department of Energy's Oak Ridge National Laboratory, in partnership with the Nuclear Science User Facilities (NSUF), provides researchers from universities, industry, and other national labs fully funded access to ORNL's dedicated nuclear infrastructure and expertise to study nuclear fuels and materials.  ORNL...

Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1-3

Journal: Nuclear Engineering and Design

The Consortium for Advanced Simulation of Light Water Reactors (CASL) aims to provide high-fidelity multi-physics simulations of light water nuclear reactors. To accomplish this, CASL is developing the Virtual Environment for Reactor Applications (VERA), which is a suite of code packages for thermal hydraulics,...

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...

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...

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...

Dimensional stability and anisotrophy of SiC and SiC-based composites in transition swelling regime

Journal: Journal of Nuclear Materials

Swelling, or volumetric expansion, is an inevitable consequence of the atomic displacement damage in crystalline silicon carbide (SiC) caused by energetic neutron irradiation. Because of its steep temperature and dose dependence, understanding swelling is essential for designing SiC-based components for nuclear...

Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

Journal: Journal of Nuclear Materials

FeCrAl alloys with varying compositions and microstructures are under consideration for accident-tolerant fuel cladding, but limited details exist on dislocation loop formation and growth for this class of alloys under neutron irradiation. Four model FeCrAl alloys with chromium contents ranging from 10.01 to 17.51 wt...

Improving variance estimation in Monte Carlo eigenvalue simulations

Journal: Annals of Nuclear Energy

Monte Carlo (MC) methods have been widely used to solve eigenvalue problems in complex nuclear systems. Once a stationary fission source is obtained in MC simulations, the sample mean of many stationary cycles is calculated. Variance or standard deviation of the sample mean is needed to indicate the level of...

Jet stability and wall impingement flow field in a thermal striping experiment

Journal: International Journal of Heat and Mass Transfer

We present velocity and temperature field measurements for a 0.9 x 0.9 x 1.7 m glass tank in which two air jets mix and impinge upon the lid at ambient temperature and pressure. At jet Re ~ 10,000, flow patterns below the lid were characterized for two inlet geometries: (1) ‘‘extended”, in which inlet channels...

Filter Publications

» Clear Filter Selections

Groups

Researchers