Olin W. Calvin , Yifeng Che , Yaqi Wang , Paolo Balestra , Javier Ortensi
{"title":"Deployment of neural-network-based neutron microscopic cross sections in the Griffin reactor physics application","authors":"Olin W. Calvin , Yifeng Che , Yaqi Wang , Paolo Balestra , Javier Ortensi","doi":"10.1016/j.anucene.2025.111509","DOIUrl":null,"url":null,"abstract":"<div><div>The use of reduced-order models for the efficient evaluation of microscopic cross sections has shown significant promise in Griffin reactor physics applications. Among various reduced-order techniques, neural network-based models stand out for their exceptional scalability, memory efficiency, prediction speed, and compatibility with the MOOSE (Multiphysics Object-Oriented Simulation Environment) framework. This work develops capabilities into the Griffin reactor physics application to utilize neural networks to predict microscopic cross-section parametric spaces for a variety of nuclides. The LibTorch interface enables Griffin’s MOOSE based materials to interact with LibTorch-trained models, allowing for the evaluation of complex microscopic cross-section spaces, which are then used to evaluate the neutronic properties of the Griffin finite-element model. This study benchmarks traditional ISOXML-formatted tabulation libraries against neural-network-based models for 279 nuclides on 20,160 grid points for zero- and two-dimensional reactor models. Benchmark metrics include the fundamental mode eigenvalue, fission and absorption rates, and various temperature coefficients of reactivity (isothermal, fuel, and moderator). From the perspective of storage space, the complete set of LibTorch models uses 11 MB, compared to the 10 GB for the ISOXML multigroup library that covers the same grid space. For the two-dimensional performance case considered in Griffin, the LibTorch model uses 97% less random access memory than the reference ISOXML dataset while runtime increases by a factor of 3 when using the LibTorch model compared to the ISOXML dataset with multilinear interpolation. The LibTorch model consistently yields errors within 0.01% for most analyzed quantities except for the temperature coefficients of reactivity where the maximum discrepancies are up to 0.3 <span><math><mfrac><mrow><mtext>pcm</mtext></mrow><mrow><mtext>K</mtext></mrow></mfrac></math></span>. Due to the neural network attempting to best predict quantities with no regard for a positive or negative bias for any given quantity, predictions may experience random fluctuations, resulting in both positive and negative errors. Future work will entail both a depletion and coupled transient analysis to determine the predictive capabilities of Griffin with neural-network-based cross sections.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111509"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925003263","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The use of reduced-order models for the efficient evaluation of microscopic cross sections has shown significant promise in Griffin reactor physics applications. Among various reduced-order techniques, neural network-based models stand out for their exceptional scalability, memory efficiency, prediction speed, and compatibility with the MOOSE (Multiphysics Object-Oriented Simulation Environment) framework. This work develops capabilities into the Griffin reactor physics application to utilize neural networks to predict microscopic cross-section parametric spaces for a variety of nuclides. The LibTorch interface enables Griffin’s MOOSE based materials to interact with LibTorch-trained models, allowing for the evaluation of complex microscopic cross-section spaces, which are then used to evaluate the neutronic properties of the Griffin finite-element model. This study benchmarks traditional ISOXML-formatted tabulation libraries against neural-network-based models for 279 nuclides on 20,160 grid points for zero- and two-dimensional reactor models. Benchmark metrics include the fundamental mode eigenvalue, fission and absorption rates, and various temperature coefficients of reactivity (isothermal, fuel, and moderator). From the perspective of storage space, the complete set of LibTorch models uses 11 MB, compared to the 10 GB for the ISOXML multigroup library that covers the same grid space. For the two-dimensional performance case considered in Griffin, the LibTorch model uses 97% less random access memory than the reference ISOXML dataset while runtime increases by a factor of 3 when using the LibTorch model compared to the ISOXML dataset with multilinear interpolation. The LibTorch model consistently yields errors within 0.01% for most analyzed quantities except for the temperature coefficients of reactivity where the maximum discrepancies are up to 0.3 . Due to the neural network attempting to best predict quantities with no regard for a positive or negative bias for any given quantity, predictions may experience random fluctuations, resulting in both positive and negative errors. Future work will entail both a depletion and coupled transient analysis to determine the predictive capabilities of Griffin with neural-network-based cross sections.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.