Amir Ali

Profile Information
Name
Prof. Amir Ali
Institution
Idaho State University
Position
Associate Professor
Affiliation
Idaho State University / Center for Advanced Energy Studies (CAES)
h-Index
13
ORCID
0000-0002-5373-3705
Biography

Dr. Amir Ali joined the Nuclear Engineering Department at Idaho State University in fall 2019. His research focuses on the experimental and computational analysis of the thermal-hydraulic challenges associated with advanced reactors, molten salt, and liquid metal-cooled reactors. Before joining the faculty at ISU, Dr. Ali served as a Research Assistant Professor at the University of New Mexico (UNM). He was a member of the thermal-hydraulic and reactor safety lab, where he researched multiple projects in the DOE-funded Nuclear Energy University Program (NEUP) and Integrated Research Projects (IRP), collaborating with national universities, laboratories, and industry. His NEUP and IRP research focused on developing a heat exchanger for advanced reactors and investigating the heat transfer performance of Accident Tolerant Fuel (ATF). Dr. Ali also worked on collaborative projects to generate validation experiments for fuel performance simulation codes in INL’s Nuclear Energy Advanced Modeling and Simulation Program.  He possesses the experience of building small-scale molten salt loops for investigating accelerated corrosion of structural alloys in FLiBe. Ali’s other research focus areas include microreactors, heat pipe technology, energy storage systems, and boiling heat transfer on micro-structured surfaces for immersion cooling applications. Ali has also been a mechanical engineering consultant for energy building systems, including fire protection, HVAC, and plumbing systems. Ali is a member of the American Society of Mechanical Engineering (ASME) and American Nuclear Society (ANS) and is a reviewer for several engineering journals.

Expertise
Accident Tolerant Fuel, Liquid Metals Reactors, Thermal Hydraulics
Additional Publications:
"Dynamic Behavior of Oval-Twisted Helical Tube Heat Exchanger: Numerical Study with RELAP5-3D" Ahmed Hamed, Palash Bhowmik, Piyush Sabharwall, George Mesina, Amir Ali, Scott Wahlquist, [2025] Nuclear Technology · DOI: 10.1080/00295450.2025.2521880
"Development of novel oval-twisted helical tube once-through steam generator: Part I: Single-phase laminar flow" Amir Ali, Kyle Schroeder, Su-Jong Yoon, Piyush Sabharwall, Scott Wahlquist, [2025] Progress in Nuclear Energy · DOI: 10.1016/j.pnucene.2025.105667
"Roles of Modeling and Artificial Intelligence in LPBF Metal Print Defect Detection: Critical Review" Amir Ali, Scott Wahlquist, [2024] Applied Sciences · DOI: 10.3390/app14188534

The integration of LPBF printing technologies in various innovative applications relies on the resilience and reliability of parts and their quality. Reducing or eliminating the factors leading to defects in final parts is crucial to producing satisfactory high-quality parts. Extensive efforts have been made to understand the material properties and printing process parameters of LPBF-printed geometries that trigger defects. Studies of interest include the use of various sensing technologies, numerical modeling, and artificial intelligence (AI) to enable a better understanding of the phenomena under investigation. The primary objectives of this article are to introduce the reader to the most widely read published data on (1) the roles of numerical and analytical models in LPBF defect detection; (2) AI algorithms and models applicable to predict LPBF metal defects and causes; and (3) the integration of modeling, AI, and sensing technology, which is commonly used in material characterization and has been proven efficient and applicable to LPBF metal part defect detection over extended periods.

"Critical Review of LPBF Metal Print Defects Detection: Roles of Selective Sensing Technology" Scott Wahlquist, Amir Ali, Donna Guillen, [2024] Applied Sciences · DOI: 10.3390/app14156718

The integrative potential of LPBF-printed parts for various innovative applications depends upon the robustness and infallibility of the part quality. Eliminating or sufficiently reducing factors contributing to the formation of defects is an integral step to achieving satisfiable part quality. Significant research efforts have been conducted to understand and quantify the triggers and origins of LPBF defects by investigating the material properties and process parameters for LPBF-printed geometries using various sensing technologies and techniques. Frequently, combinations of sensing techniques are applied to deepen the understanding of the investigated phenomena. The main objectives of this review are to cover the roles of selective sensing technologies by (1) providing a summary of LPBF metal print defects and their corresponding causes, (2) informing readers of the vast number and types of technologies and methodologies available to detect defects in LPBF-printed parts, and (3) equipping readers with publications geared towards defect detection using combinations of sensing technologies. Due to the large pool of developed sensing technology in the last few years for LPBF-printed parts that may be designed for targeting a specific defect in metal alloys, the article herein focuses on sensing technology that is common and applicable to most common defects and has been utilized in characterization for an extended period with proven efficiency and applicability to LPBF metal parts defect detection.

"A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications" Joshua Hansel, Piyush Sabharwall, Amir Ali, Scott Wahlquist, [2023] Nuclear Science and Engineering · DOI: 10.1080/00295639.2022.2082230
"Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces" Amir Ali, Minghui Chen, Mingfu He, [2022] Progress in Nuclear Energy · DOI: 10.1016/j.pnucene.2022.104211
"Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux" Hyun-Gil Kim, Khalid Hattar, Samuel Briggs, Dong Jun Park, Jung Hwan Park, Youho Lee, Amir Ali, [2020] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2020.110581
"Chemical Head Loss Measurements on Multi-Constituent Debris Beds in Small-Scale Experiments" Kerry J. Howe, Edward D. Blandford, Amir Ali, [2018] Nuclear Technology · DOI: 10.1080/00295450.2018.1480212
"Conceptual design of a freeze-tolerant Direct Reactor Auxiliary Cooling System for Fluoride-salt-cooled High-temperature Reactors" Joel Hughes, Amir Ali, Edward Blandford, Maolong Liu, [2018] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2018.04.019
"Corrosion and solubility in a TSP-buffered chemical environment following a loss of coolant accident: Part 2 – Zinc" Daniel LaBrier, Amir Ali, Edward D. Blandford, Kerry J. Howe, David Pease, [2016] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2015.09.036
Source: ORCID/CrossRef using DOI