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Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs

Description: The generation of multigroup cross sections lies at the heart of the very high temperature reactor (VHTR) core design, whether the prismatic (block) or pebble-bed type. The design process, generally performed in three steps, is quite involved and its execution is crucial to proper reactor physics analyses. The primary purpose of this project is to develop the CENTRM cross-section processing module of the SCALE code package for application to prismatic or pebble-bed core designs. The team will i… more
Date: January 23, 2014
Creator: Ganapol, Barry & Maldonado, Ivan
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels

Description: Enhancing performance of fuel cladding and duct alloys is a key means of increasing fuel burnup. This project will address the failure of fuel cladding via three-dimensional cracking models. Researchers will develop a simulation code for the failure of the fuel cladding and validate the code through experiments. The objective is to develop an algorithm to determine the failure of fuel cladding in the form of three-dimensional cracking due to prolonged exposure under varying conditions of pressu… more
Date: January 9, 2014
Creator: Lu, Hongbing; Bukkapatnam, Satish; Harimkar, Sandip; Singh, Raman & Bardenhagen, Scott
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature: Critical Experiments

Description: The in-service degradation of reactor core materials is related to underlying changes in the irradiated microstructure. During reactor operation, structural components and cladding experience displacement of atoms by collisions with neutrons at temperatures at which the radiation-induced defects are mobile, leading to microstructure evolution under irradiation that can degrade material properties. At the doses and temperatures relevant to fast reactor operation, the microstructure evolves by mi… more
Date: December 20, 2013
Creator: Was, Gary; Jiao, Zhijie; Allen, Todd & Yang, Yong
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids

Description: The research team has developed a practical, high-order, discrete-ordinates, short characteristics neutron transport code for three-dimensional configurations represented on unstructured tetrahedral grids that can be used for realistic reactor physics applications at both the assembly and core levels. This project will perform a comprehensive verification and validation of this new computational tool against both a continuous-energy Monte Carlo simulation (e.g. MCNP) and experimentally measured… more
Date: December 20, 2013
Creator: Azmy, Yousry & Wang, Yaqi
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation: Modeling and Experimental Investigation

Description: The in-service degradation of reactor core materials is related to underlying changes in the irradiated microstructure. During reactor operation, structural components and cladding experience displacement of atoms by collisions with neutrons at temperatures at which the radiation-induced defects are mobile, leading to microstructure evolution under irradiation that can degrade material properties. At the doses and temperatures relevant to fast reactor operation, the microstructure evolves by di… more
Date: December 1, 2013
Creator: Wirth, Brian; Morgan, Dane; Kaoumi, Djamel & Motta, Arthur
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consistent Multigroup Theory Enabling Accurate Course-Group Simulation of Gen IV Reactors

Description: The objective of this proposal is the development of a consistent multi-group theory that accurately accounts for the energy-angle coupling associated with collapsed-group cross sections. This will allow for coarse-group transport and diffusion theory calculations that exhibit continuous energy accuracy and implicitly treat cross- section resonances. This is of particular importance when considering the highly heterogeneous and optically thin reactor designs within the Next Generation Nuclear P… more
Date: November 29, 2013
Creator: Rahnema, Farzad; Haghighat, Alireza & Ougouag, Abderrafi
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors

Description: This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state and transient analyses in advanced very high-temperature reactors (VHTRs). The project will lead to a coupled neutronics and thermal hydraulic (T/H) core simulation tool with fuel depletion capability. The computational tool will be developed in hexagonal geometry, based solely on transport theory without (spatial) homogenization in complicated 3D geometries. In addition to the hexagonal geometry… more
Date: November 29, 2013
Creator: Rahnema, Farzad; Garimeela, Srinivas; Ougouag, Abderrafi & Zhang, Dingkang
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors

Description: The goal of this research project is to develop the methods and tools necessary to link unit processes analyzed using atomistic simulations involving interaction of vacancies and interstitials with dislocations, as well as dislocation mediation at sessile junctions and interfaces as affected by radiation, with cooperative influence on higher-length scale behavior of polycrystals. These tools and methods are necessary to design and enhance radiation-induced damage-tolerant alloys. The project wi… more
Date: November 17, 2013
Creator: Deo, Chaitanya; Zhu, Ting & McDowell, David
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation on the Core Bypass Flow in a Very High Temperature Reactor

Description: Uncertainties associated with the core bypass flow are some of the key issues that directly influence the coolant mass flow distribution and magnitude, and thus the operational core temperature profiles, in the very high-temperature reactor (VHTR). Designers will attempt to configure the core geometry so the core cooling flow rate magnitude and distribution conform to the design values. The objective of this project is to study the bypass flow both experimentally and computationally. Researcher… more
Date: October 22, 2013
Creator: Hassan, Yassin
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Development and Demonstration of Ultrasonic Measurement Diagnostics for Sodium Fast Reactor Thermal-hydraulics

Description: This research project will address some of the principal technology issues related to sodium-cooled fast reactors (SFR), primarily the development and demonstration of ultrasonic measurement diagnostics linked to effective thermal convective sensing under normatl and off-normal conditions. Sodium is well-suited as a heat transfer medium for the SFR. However, because it is chemically reactive and optically opaque, it presents engineering accessibility constraints relative to operations and maint… more
Date: September 13, 2013
Creator: Tokuhiro, Akira & Jones, Byron
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modeling Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components

Description: This project will implement inelastic constitutive models that will yield the requisite stress-strain information necessary for graphite component design. Accurate knowledge of stress states (both elastic and inelastic) is required to assess how close a nuclear core component is to failure. Strain states are needed to assess deformations in order to ascertain serviceability issues relating to failure, e.g., whether too much shrinkage has taken place for the core to function properly. Failure pr… more
Date: September 9, 2013
Creator: Duffy, Stephen
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Technical Basis and Guidance for Advanced SMR Function Allocation

Description: This report presents the results from three key activities for FY13 that influence the definition of new concepts of operations for advanced Small Modular Reactors (AdvSMR: a) the development of a framework for the analysis of the functional environmental, and structural attributes, b) the effect that new technologies and operational concepts would have on the way functions are allocated to humans or machines or combinations of the two, and c) the relationship between new concepts of operations… more
Date: September 1, 2013
Creator: Hugo, Jacques; Gertman, David; Joe, Jeffrey; Farris, Ronal; Whaley, April & Medema, Heather
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Concepts for Mulitiple Application Thermal Reactor for Irradiation eXperiments (MATRIX)

Description: The Advanced Test Reactor (ATR) is a high power density test reactor specializing in fuel and materials irradiation. For more than 45 years, the ATR has provided irradiations of materials and fuels testing along with radioisotope production. Originally operated primarily in support of the Offcie of Naval Reactors (NR), the mission has gradually expanded to cater to other customers, such as the DOE Office of Nuclear Energy (NE), private industry, and universities. Unforeseen circumstances may le… more
Date: September 1, 2013
Creator: Pope, Michael A.; Gougar, Hans D. & Ryskamp, John M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Letter Report: Looking Ahead at Nuclear Fuel Resources

Description: The future of nuclear energy and its ability to fulfill part of the world’s energy needs for centuries to come depend on a reliable input of nuclear fuel, either thorium or uranium. Obviously, the present nuclear fuel cycle is completely dependent on uranium. Future thorium cycles will also depend on 235U or fissile isotopes separated from used fuel to breed 232Th into fissile 233U. This letter report discusses several emerging areas of scientific understanding and technology development that w… more
Date: September 1, 2013
Creator: Herring, J. Stephen
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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