scholarly journals As-Built Simulation of the High Flux Isotope Reactor

2021 ◽  
Vol 2 (1) ◽  
pp. 28-34
Author(s):  
Benjamin R. Betzler ◽  
David Chandler ◽  
Thomas M. Evans ◽  
Gregory G. Davidson ◽  
Charles R. Daily ◽  
...  
Keyword(s):  
Fuel Element ◽  
National Laboratory ◽  
Thermal Flux ◽  
Three Dimensional ◽  
Control Element ◽  
High Flux ◽  
Oak Ridge ◽  
Power Profile ◽  
Enriched Uranium ◽  
Fuel Meat

The Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) is an 85 MWt flux trap-type research reactor that supports key research missions, including isotope production, materials irradiation, and neutron scattering. The core consists of an inner and an outer fuel element containing 171 and 369 involute-shaped plates, respectively. The thin fuel plates consist of a U3O8-Al dispersion fuel (highly enriched), an aluminum-based filler, and aluminum cladding. The fuel meat thickness is varied across the width of the involute plate to reduce thermal flux peaks at the radial edges of the fuel elements. Some deviation from the designed fuel meat shaping is allowed during manufacturing. A homogeneity scan of each fuel plate checks for potential anomalies in the fuel distribution by scanning the surface of the plate and comparing the attenuation of the beam to calibration standards. While typical HFIR simulations use homogenized fuel regions, explicit models of the plates were developed under the Low-Enriched Uranium Conversion Program. These explicit models typically include one inner and one outer fuel plate with nominal fuel distributions, and then the plates are duplicated to fill the space of the corresponding fuel element. Therefore, data extracted from these simulations are limited to azimuthally averaged quantities. To determine the reactivity and physics impacts of an as-built outer fuel element and generate azimuthally dependent data in the element, 369 unique fuel plate models were generated and positioned. This model generates the three-dimensional (i.e., radial–axial–azimuthal) plate power profile, where the azimuthal profile is impacted by features within the adjacent control element region and beryllium reflector. For an as-built model of the outer fuel element, plate-specific homogeneity data, 235U loading, enrichment, and channel thickness measurements were translated into the model, yielding a much more varied azimuthal power profile encompassed by uncertainty factors in analyses. These models were run with the ORNL-TN and Shift Monte Carlo tools, and they contained upwards of 500,000 cells and 100,000 unique tallies.

scholarly journals REACTOR PERFORMANCE IMPROVEMENT OPTIONS TO SUSTAIN HIGH FLUX ISOTOPE REACTOR LEADERSHIP INTO THE FUTURE*

2021 ◽  
Vol 247 ◽  
pp. 08016
Author(s):  
D. Chandler ◽  
B. R. Betzler ◽  
D. H. Cook
Keyword(s):  
Neutron Scattering ◽  
Materials Science ◽  
National Laboratory ◽  
High Flux ◽  
Reactor Performance ◽  
Oak Ridge ◽  
Cold Source ◽  
The Future ◽  
Materials Science And Engineering ◽  
Enriched Uranium

The mission of the Neutron Sciences Directorate (NScD) at the U.S. Department of Energy’s Oak Ridge National Laboratory (ORNL) is the undertaking of high-impact research into the structure and properties of materials across the spectrum of biology, chemistry, physics, materials science, and engineering. NScD operates two world-leading neutron scattering facilities: the High Flux Isotope Reactor (HFIR) and the Spallation Neutron Source. HFIR achieved full power in 1966, and over a half century later, it continues to serve a variety of national missions. HFIR provides one of the highest steady-state neutron fluxes of any research reactor in the world to support scientific missions including cold and thermal neutron scattering, isotope production, and materials irradiation research. To sustain leadership in neutron sciences into the future, ORNL is exploring areas in which HFIR can be improved to enhance its performance. Many improvement areas are being explored including upgrading the cold source and neutron scattering facilities. The improvement areas discussed herein include replacing the reactor pressure vessel, upgrading the neutron reflector, and ensuring that reactor performance is maintained or enhanced after converting from high-enriched uranium to low-enriched uranium fuel.

scholarly journals The CG-1D Neutron Imaging Beamline at the Oak Ridge National Laboratory High Flux Isotope Reactor

2015 ◽  
Vol 69 ◽  
pp. 104-108 ◽  
Author(s):  
Lou Santodonato ◽  
Hassina Bilheux ◽  
Barton Bailey ◽  
Jean Bilheux ◽  
Phong Nguyen ◽  
...  
Keyword(s):  
National Laboratory ◽  
Neutron Imaging ◽  
High Flux ◽  
Oak Ridge ◽  
Oak Ridge National Laboratory

scholarly journals The suite of small-angle neutron scattering instruments at Oak Ridge National Laboratory

2018 ◽  
Vol 51 (2) ◽  
pp. 242-248 ◽  
Author(s):  
William T. Heller ◽  
Matthew Cuneo ◽  
Lisa Debeer-Schmitt ◽  
Changwoo Do ◽  
Lilin He ◽  
...  
Keyword(s):  
Neutron Scattering ◽  
Small Angle ◽  
Small Angle Neutron Scattering ◽  
Large Scale ◽  
National Laboratory ◽  
High Flux ◽  
Oak Ridge ◽  
Large Scale Structures ◽  
Oak Ridge National Laboratory ◽  
Scale Structures

Oak Ridge National Laboratory is home to the High Flux Isotope Reactor (HFIR), a high-flux research reactor, and the Spallation Neutron Source (SNS), the world's most intense source of pulsed neutron beams. The unique co-localization of these two sources provided an opportunity to develop a suite of complementary small-angle neutron scattering instruments for studies of large-scale structures: the GP-SANS and Bio-SANS instruments at the HFIR and the EQ-SANS and TOF-USANS instruments at the SNS. This article provides an overview of the capabilities of the suite of instruments, with specific emphasis on how they complement each other. A description of the plans for future developments including greater integration of the suite into a single point of entry for neutron scattering studies of large-scale structures is also provided.

The Use and Refinement of Neutron Imaging Techniques for Archaeological Artifacts

2014 ◽  
Vol 2 (2) ◽  
pp. 91-103
Author(s):  
Krysta Ryzewski ◽  
Hassina Z. Bilheux ◽  
Susan N. Herringer ◽  
Jean-Christophe Bilheux ◽  
Lakeisha Walker ◽  
...  
Keyword(s):  
Materials Science ◽  
Imaging Techniques ◽  
National Laboratory ◽  
Three Dimensional ◽  
Neutron Imaging ◽  
Three Dimensions ◽  
Imaging Data ◽  
Oak Ridge ◽  
Dual Objectives ◽  
Archaeological Objects

AbstractNeutron imaging is a nondestructive application capable of producing two- and three-dimensional maps of archaeological objects’ external and internal structure, properties, and composition. This report presents the recent development of neutron imaging data collection and processing methods at Oak Ridge National Laboratory (ORNL), which have been advanced, in part, by information gathered from the experimental imaging of 25 archaeological objects over the past three years. The dual objectives of these imaging experiments included (1) establishing the first methodological procedures for the neutron imaging of archaeomaterials involving the CG-1D beamline and (2) further illustrating the potential of neutron imaging for archaeologists to use in the reverse engineering of ancient and historical objects. Examples of objects imaged in two and three dimensions are provided to highlight the application’s strengths and limitations for archaeological investigations, especially those that address ancient and historic technologies, materials science, and conservation issues.

scholarly journals Conceptual Design of a MEDE Treatment System for Sodium Bonded Fuel

2008 ◽  
Author(s):  
Carl E. Baily ◽  
Karen A. Moore ◽  
Collin J. Knight ◽  
Peter B. Wells ◽  
Paul J. Petersen ◽  
...  
Keyword(s):  
Spent Nuclear Fuel ◽  
National Laboratory ◽  
Department Of Energy ◽  
Test Facility ◽  
Evaporation Chamber ◽  
Oak Ridge ◽  
Uranium Fuel ◽  
Fuel Assemblies ◽  
Metal Fuel ◽  
Enriched Uranium

Unirradiated sodium bonded metal fuel and casting scrap material containing highly enriched uranium (HEU) is stored at the Materials and Fuels Complex (MFC) on the Idaho National Laboratory (INL). This material, which includes intact fuel assemblies and elements from the Fast Flux Test Facility (FFTF) and Experimental Breeder Reactor-II (EBR-II) reactors, as well as scrap material from the casting of these fuels, has no current use under the terminated reactor programs for both facilities. The Department of Energy (DOE), under the Sodium-Bonded Spent Nuclear Fuel Treatment Record of Decision (ROD), has determined that this material could be prepared and transferred to an off-site facility for processing and eventual fabrication of fuel for commercial nuclear reactors. A plan is being developed to prepare, package, and transfer this material to the DOE HEU Disposition Program Office (HDPO), located at the Y-12 National Security Complex in Oak Ridge, Tennessee. Disposition of the sodium bonded material will require separating the elemental sodium from the metallic uranium fuel. A sodium distillation process known as MEDE (Melt-Drain-Evaporate), will be used for the separation process. The casting scrap material needs to be sorted to remove any foreign material or fines that are not acceptable to the HDPO program. Once all elements have been cut and loaded into baskets, they are then loaded into an evaporation chamber as the first step in the MEDE process. The chamber will be sealed and the pressure reduced to approximately 200 mtorr. The chamber will then be heated as high as 650 °C, causing the sodium to melt and then vaporize. The vapor phase sodium will be driven into an outlet line where it is condensed and drained into a receiver vessel. Once the evaporation operation is complete, the system is de-energized and returned to atmospheric pressure. This paper describes the MEDE process as well as a general overview of the furnace systems, as necessary, to complete the MEDE process.

Seismic Evaluation of the Oak Ridge National Laboratory High Flux Isotope Reactor Support Assembly

2006 ◽  
Author(s):  
Gustavo A. Aramayo
Keyword(s):  
Structural Component ◽  
National Laboratory ◽  
Department Of Energy ◽  
Seismic Excitation ◽  
High Flux ◽  
Seismic Evaluation ◽  
Oak Ridge ◽  
Oak Ridge National Laboratory

The support assembly of the Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) was modeled to determine the assembly’s response to a seismic excitation. The compliance of this structural component to established U. S. Department of Energy (USDOE) standards [1, 2] is evaluated.

A Three-Dimensional Analysis of the Local Stresses and Strains at the Pellet Ridges in a Horizontal Nuclear Fuel Element

2014 ◽  
Author(s):  
Kyle A. L. Gamble ◽  
Anthony F. Williams ◽  
Paul K. Chan
Keyword(s):  
Fuel Element ◽  
Nuclear Fuel ◽  
National Laboratory ◽  
Three Dimensional ◽  
Diffusional Creep ◽  
Creep Model ◽  
Elastic Model ◽  
Hoop Strain ◽  
Nuclear Fuel Element ◽  
Local Stresses

A three-dimensional finite element model is being developed for a quarter fuel element, which is equivalent to a full fuel element using symmetry. The model uses the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework developed at Idaho National Laboratory. The model facilitates an in-depth investigation into a variety of deformation phenomena for a horizontal nuclear fuel element including bowing, sagging, and stresses and strains. This paper presents a preliminary analysis of the local stresses and strains of the sheath (clad) at the pellet-to-pellet interfaces for low, normal and high linear powers. During irradiation the fuel pellets thermally expand and take on an hourglass shape. The hourglassing behaviour leads to higher local stresses and strains in the sheath at the locations of the pellet-to-pellet interfaces. The purpose of this work is to quantify these stresses and strains for varying linear powers, and to illustrate the effect that the material model chosen for the cladding has on the results. Preliminary results are presented for two sheath types: elastic, and elastic including diffusional creep. These models are benchmarked against a validated industry code called ELESTRES. The results indicate that the predicted sheath hoop strain is about half of what is determined by ELESTRES in both the elastic and elastic-creep cases. This highlights the requirement of a pellet cracking model in three-dimensional simulations. The elastic-creep model predicts less stress within the sheath than the elastic model as expected.

Additive Manufacturing Integrated Energy—Enabling Innovative Solutions for Buildings of the Future

2016 ◽  
Vol 139 (1) ◽  
Author(s):  
Kaushik Biswas ◽  
James Rose ◽  
Leif Eikevik ◽  
Maged Guerguis ◽  
Philip Enquist ◽  
...  
Keyword(s):  
Additive Manufacturing ◽  
National Laboratory ◽  
Three Dimensional ◽  
University Of Tennessee ◽  
Oak Ridge ◽  
Construction Methods ◽  
Integrate Structure ◽  
Architecture And Design ◽  
The University ◽  
First Time

The additive manufacturing integrated energy (AMIE) demonstration utilized three-dimensional (3D) printing as an enabling technology in the pursuit of construction methods that use less material, create less waste, and require less energy to build and operate. Developed by Oak Ridge National Laboratory (ORNL) in collaboration with the Governor's Chair for Energy and Urbanism, a research partnership of the University of Tennessee (UT) and ORNL led by Skidmore, Owings & Merrill LLP (SOM), AMIE embodies a suite of innovations demonstrating a transformative future for designing, constructing, and operating buildings. Subsequent, independent UT College of Architecture and Design studios taught in collaboration with SOM professionals also explored forms and shapes based on biological systems that naturally integrate structure and enclosure. AMIE, a compact microdwelling developed by ORNL research scientists and SOM designers, incorporates next-generation modified atmosphere insulation (MAI), self-shading windows, and the ability to produce, store, and share solar power with a paired hybrid vehicle. It establishes for the first time, a platform for investigating solutions integrating the energy systems in buildings, vehicles, and the power grid. The project was built with broad-based support from local industry and national material suppliers. Designed and constructed in a span of only 9 months, AMIE 1.0 serves as an example of the rapid innovation that can be accomplished when research, design, academic, and industrial partners work in collaboration toward the common goal of a more sustainable and resilient built environment.

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