Engineering Papers⌕ Search
Home/Archive/DOE OSTI

DOE OSTI · 2572857

Multi-Scale Modeling of the Evolution of Structure and Properties in Materials for Nuclear Energy Applications [Slides]

Aagesen Jr, Larry Kenneth [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:000000034936676X)·Biswas, Sudipta [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000292788020)·Pitts, Stephanie A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000242996606)·Simon, Pierre-Clement A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000170832628)·Cooper, Michael [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)]·Galvin, Conor [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)]·Andersson, David [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)]·Blondel, Sophie [Univ. of Tennessee, Knoxville, TN (United States)]·Jiang, Wen [North Carolina State University, Raleigh, NC (United States)]·Hermawan, Danny [Purdue Univ., West Lafayette, IN (United States)]·Garcia, Edwin [Purdue Univ., West Lafayette, IN (United States)]
View original source ↗Read source document ↗Export metadata ↓

Abstract

Nuclear energy is an important component of an overall strategy to address climate change. Idaho National Laboratory (INL) is the U.S. Department of Energy’s primary facility for research and development in nuclear science and technology for energy generation, supporting the improvement and life extension of the existing reactor fleet and the development and licensing of new reactor designs. Computational modeling is an important component of these activities, particularly in the area of materials for nuclear applications, where experimental data can be very challenging and expensive to acquire, and where data is especially scarce for new reactor designs. INL has used multi-scale modeling – linking atomistic, mesoscale, and engineering scales – to improve the ability to predict the performance of materials for nuclear energy applications. In this talk, I will give an overview of the approach and tools used, and several examples of application, including performance of nuclear fuels, understanding radiation-driven formation of nanoscale void and gas bubble superlattices, and powder densification through electric field assisted sintering.

Explore related subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS36 MATERIALS SCIENCEEFAShigh burnupphase-fieldpulverizationSPS

Keep this discovery

Explore connections, maps & timelines

BibTeXRIS

Aagesen Jr, Larry Kenneth [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:000000034936676X), Biswas, Sudipta [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000292788020), Pitts, Stephanie A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000242996606), Simon, Pierre-Clement A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000170832628), Cooper, Michael [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)], Galvin, Conor [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)], Andersson, David [Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)], Blondel, Sophie [Univ. of Tennessee, Knoxville, TN (United States)], Jiang, Wen [North Carolina State University, Raleigh, NC (United States)], Hermawan, Danny [Purdue Univ., West Lafayette, IN (United States)], Garcia, Edwin [Purdue Univ., West Lafayette, IN (United States)]. 2025-04-25. Multi-Scale Modeling of the Evolution of Structure and Properties in Materials for Nuclear Energy Applications [Slides]. https://doi.org/10.2172/2572857

Cite the original work for its findings. Save a collection to share your selection of sources.

KEEP EXPLORING

Related reports

DOE OSTI2026

ZiaCore Critical Experiment Demonstrates Key Technologies for Nuclear Energy Systems

ZiaCore is a LANL Laboratory Directed Research and Development (LDRD) project focused on developing and demonstrating key technologies for future nuclear energy systems. The project itself was split into three tasks: 1) Design of the ZiaCore Reactor, a UO2 fueled, graphite and zirconium-hydride (ZrH) moderated, heat pipe cooled micro-reactor 2) Development of the ZrH and heat pipes components 3) Performance of a critical experiment with a representative portion of the ZiaCore reactor incorporating the ZrH and heat pipes developed and made at LANL.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2026

Operating Experience Data Analysis for Digital Instrumentation and Control System Reliability and Risk Assessment in Nuclear Power Plants

The implementation of advanced digital instrumentation and control (DI&C) systems in U.S. nuclear power plants (NPPs) can bring significant advancements in reliability, monitoring, and control capabilities. However, these systems also introduce new challenges, particularly in assessing risks such as common-cause failures (CCFs) and establishing robust reliability estimates for DI&C components. Addressing these challenges is critical for ensuring the safe and efficient operation of NPPs. Recently, Idaho National Laboratory was tasked by the U.S. Nuclear Regulatory Commission (NRC) to conduct a DI&C reliability study using operating experience data from the nuclear industry. The two operating experience data sources for the study are the Institute of Nuclear Power Operations’ Industry Reporting and Information System (IRIS) and the NRC’s Licensee Event Report database which is hosted at Idaho National Laboratory at https://lersearch.inl.gov/LERSearchCriteria.aspx. This report provides a comprehensive examination of DI&C systems, including their architecture, operational advantages, and associated challenges. It reviews existing industry DI&C studies and failure mode taxonomies, along with reliability data from various industries. Through a detailed analysis of these databases, the study provides insights into DI&C system performance. Considerations should be given to incorporate DI&C failure data into the NRC's Integrated Data Collection and Coding System and updating the Reliability and Availability Data System to support ongoing DI&C reliability studies. Recommendations are also provided for modeling DI&C reliability and CCF in probabilistic risk assessment, thereby supporting risk-informed decision-making and enhancing the reliability and safety of NPPs.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗