Mehdi Asgari
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View article: A High-Fidelity Model of the Peach Bottom 2 Turbine-Trip Benchmark Using VERA
A High-Fidelity Model of the Peach Bottom 2 Turbine-Trip Benchmark Using VERA Open
This work presents a high-fidelity simulation of the Peach Bottom turbine trip (PBTT) benchmark using the Virtual Environment for Reactor Applications (VERA), a multiphysics reactor modeling tool developed by the U.S. Department of Energy’…
View article: High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration
High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration Open
Nuclear power currently contributes approximately 20% of total electricity generation in the United States and more than 10% globally. Given the increasing reliance on nuclear energy to achieve our nation’s goal of reaching net-zero carbon…
View article: Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor
Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor Open
The SCALE/Polaris–PARCS code procedure has been used in the confirmatory analysis for boiling water reactors by the US Nuclear Regulatory Commission. In this study, the SCALE/Polaris v6.3.0–PARCS v3.4.2 code procedure with the Evaluated Nu…
View article: Sub-Pin Fission Product Sensitivity to Assembly and Core Models on High-Burnup Fuel and Comparison to Experimental Measurements
Sub-Pin Fission Product Sensitivity to Assembly and Core Models on High-Burnup Fuel and Comparison to Experimental Measurements Open
View article: Watts Bar I Ex-Core Analyses using VERA
Watts Bar I Ex-Core Analyses using VERA Open
The integration and direct coupling of the Oak Ridge National Laboratory (ORNL) Shift Monte Carlo code within the Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reactor Applications (VERA) offers …
View article: Assessing UN Neutronic and Fuel Performance for Extended Cycle Lengths
Assessing UN Neutronic and Fuel Performance for Extended Cycle Lengths Open
View article: MPACT Verification and Validation Manual Version 4.4
MPACT Verification and Validation Manual Version 4.4 Open
As the VERA SQA plan requires, it is the responsibility of the University of Michigan (UM) and Oak Ridge National Laboratory (ORNL), as co-owners of MPACT, to ensure that verification and validation activities are performed and documented …
View article: Pressurized Water Reactor Gadolinia Pin Location Optimization
Pressurized Water Reactor Gadolinia Pin Location Optimization Open
This report presents the results of lattice optimization studies performed to find optimum locations for gadolinia burnable absorber (BA) rods in pressurized water reactor (PWR) lattice fuel designs. Initial excess reactivity suppression a…
View article: Enhanced LWR High Burnup Transient Simulation Capabilities to Support AOO Margin Identification
Enhanced LWR High Burnup Transient Simulation Capabilities to Support AOO Margin Identification Open
As part of ongoing efforts to support the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program’s development of a fuel fragmentation, relocation, and dispersal (FFRD) screening methodology, a number of improvements are required …
View article: Subchannel Methods Development for Modeling of Light-Water Reactors at Oak Ridge National Laboratory
Subchannel Methods Development for Modeling of Light-Water Reactors at Oak Ridge National Laboratory Open
View article: Bypass Flow Model Implementation for VERA BWR
Bypass Flow Model Implementation for VERA BWR Open
The Virtual Environment for Reactor Applications (VERA) has been developed by the Consortium for Advanced Simulation of LWRs (CASL) over the past 10 years to address difficult problems facing commercial light-water reactors (LWRs). VERA co…
View article: The Feasibility and the Benefits of the Advanced Nuclear Fuel Pellet Designs with Radially Varying Fuel Zoning and Burnable Poison Concentration (Final Summary Report)
The Feasibility and the Benefits of the Advanced Nuclear Fuel Pellet Designs with Radially Varying Fuel Zoning and Burnable Poison Concentration (Final Summary Report) Open
As part of the work supported by the US Department of Energy (DOE) Office of Nuclear Energy (NE) Gateway for Accelerated Innovation in Nuclear (GAIN) FY 2021 Voucher, Exelon Generation, now Constellation, and Oak Ridge National Laboratory …
View article: Investigation of convection and radiation heat transfer of paraffinic materials and storage of thermal energy in melting process of PCMs in the cavity with transparent inner walls
Investigation of convection and radiation heat transfer of paraffinic materials and storage of thermal energy in melting process of PCMs in the cavity with transparent inner walls Open
Phase change materials have wide applications as thermal energy storage systems. Due to the low thermal conductivity of these materials, lots of efforts have been made to increase the thermal conductivity and efficiency of thermal energy s…
View article: Thermal energy storage inside the chamber with a brick wall using the phase change process of paraffinic materials: A numerical simulation
Thermal energy storage inside the chamber with a brick wall using the phase change process of paraffinic materials: A numerical simulation Open
View article: LEU+ BWR Lattice Design Optimization of Using SCALE/Polaris
LEU+ BWR Lattice Design Optimization of Using SCALE/Polaris Open
View article: Preliminary Simulation Results of Peach Bottom Unit 2 Cycles 1 and 2 with MPACT
Preliminary Simulation Results of Peach Bottom Unit 2 Cycles 1 and 2 with MPACT Open
View article: VERA BWR Progression Problems
VERA BWR Progression Problems Open
View article: Multiscale Thermal Hydraulic Coupling Methods for Boiling Water Reactor Simulation
Multiscale Thermal Hydraulic Coupling Methods for Boiling Water Reactor Simulation Open
View article: Pellet Cladding Mechanical Interaction as a Potential Failure Mechanism During a Control Rod Drop Accident in a Boiling Water Reactor
Pellet Cladding Mechanical Interaction as a Potential Failure Mechanism During a Control Rod Drop Accident in a Boiling Water Reactor Open
Boiling water reactors (BWRs) represent approximately one-third of the operating fleet in the United States, contributing significantly towards the global effort in reducing carbon emissions. Even though most of the operating fleet has bee…
View article: BWR Progression Problems
BWR Progression Problems Open
Under the Consortium for the Advanced Simulation of Light Water Reactors (CASL) Program, the Virtual Environment for Reactor Applications (VERA) was developed with the primary focus to model pressurized water reactors (PWRs). Recently, a n…
View article: VERA-Grizzly Ex-Core Calculations: Watts Bar Unit 1 Cycles 1-2
VERA-Grizzly Ex-Core Calculations: Watts Bar Unit 1 Cycles 1-2 Open
The critical structures that comprise light-water reactor (LWR) nuclear power plants are subjected to operating environments that can challenge their integrity. Structures in close proximity to the reactor core, such as the reactor pressur…
View article: New Generation of Electrochemical Sensor for Sub-Nanomolar Zn (II) Ion Detection Based on Nano- Sized Ion Imprinted Polymer and Functionalized Multi-Walled Carbon Nanaotube Composite Modified Glassy Carbon Electrode
New Generation of Electrochemical Sensor for Sub-Nanomolar Zn (II) Ion Detection Based on Nano- Sized Ion Imprinted Polymer and Functionalized Multi-Walled Carbon Nanaotube Composite Modified Glassy Carbon Electrode Open
A new selective and sensitive electrochemical sensor was prepared by film coating of Zinc (II) ion imprinted polymer (IIP) nanoparticle and functionalized multi-walled carbon nanotube (MWCN) composite on glassy carbon electrode (GCE). The …
View article: Summary of CTF Modeling and Numerical Improvements for Boiling Water Reactor Simulation
Summary of CTF Modeling and Numerical Improvements for Boiling Water Reactor Simulation Open
This report documents geometry and numerical improvements made to CTF for the modeling of boiling water reactor (BWR) geometry and operating conditions. These activities are part of a larger program to extend the Virtual Environment for Re…
View article: Simulation of solidification process of phase change materials in a heat exchanger using branch-shaped fins
Simulation of solidification process of phase change materials in a heat exchanger using branch-shaped fins Open
Nowadays, due to the global need for energy and the limited amount of fossil fuels, it is required to utilize alternative forms of energy. Thermal energy storage systems together with phase change materials are considered potential options…
View article: Improvements to CTF for Modeling of Boiling Water Reactor Geometry and Operating Conditions
Improvements to CTF for Modeling of Boiling Water Reactor Geometry and Operating Conditions Open
This report documents work done to improve CTF modeling of boiling water reactor (BWR) designs during FY 2020. Several improvements were made to the geometry modeling capabilities, including adding support for modeling of inlet flow orific…
View article: Plasma Separation Process Feasibility Study for Commercial Enrichment of Gadolinium-157 (Final Report)
Plasma Separation Process Feasibility Study for Commercial Enrichment of Gadolinium-157 (Final Report) Open
The US nuclear power fleet is actively working on innovative initiatives that will reduce total fuel cycle and operations costs to stay economically competitive. Converting the natural gadolinium (Gd) currently used in US light water react…
View article: Minor Actinide Recycle in Sodium Cooled Fast Reactors Using Heterogeneous Targets
Minor Actinide Recycle in Sodium Cooled Fast Reactors Using Heterogeneous Targets Open
This paper investigates the plausible design of transmutation target assemblies for minor actinides (MA) in Sodium Fast Reactors (SFR). A heterogeneous recycling strategy is investigated, whereby after each reactor pass, un-burned MAs from…
View article: Importance of the (n,gamma) Cm-247 Evaluation on Neutron Emission in Fast Reactor Fuel Cycle Analysis
Importance of the (n,gamma) Cm-247 Evaluation on Neutron Emission in Fast Reactor Fuel Cycle Analysis Open
As part of the GNEP program, it is envisioned to build a fast reactor for the transmutation of minor actinides. The spent nuclear fuel from the current fleet of light water reactors would be recycled, the current baseline is the UREX+1a pr…