Annals of Nuclear Energy最新文献_第7页

Multi-zone cooperative reconstruction network for off-situ monitoring of the core neutron field

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111035

Pei Cao , Donghao Li , Mengfang Ren

引用次数: 0

Autonomous anomaly detection of proliferation in the AGN-201 nuclear reactor digital twin

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.110990

Eduardo Treviño , Ashley Shields , Ryan Stewart , John Darrington , Jonathan Scott , Chad Pope , Christopher Ritter

{"title":"Autonomous anomaly detection of proliferation in the AGN-201 nuclear reactor digital twin","authors":"Eduardo Treviño , Ashley Shields , Ryan Stewart , John Darrington , Jonathan Scott , Chad Pope , Christopher Ritter","doi":"10.1016/j.anucene.2024.110990","DOIUrl":"10.1016/j.anucene.2024.110990","url":null,"abstract":"<div><div>The expansion of global nuclear power necessitates advanced methods for analyzing proliferation indicators. This study introduces a novel application of the Isolation Forest Machine Learning (IFML) algorithm within a digital twin (DT) of the AGN-201 nuclear reactor to autonomously detect anomalies. Leveraging real-time operational data from the AGN-201 DT, the IFML algorithm identifies outliers without prior data labeling and operates as a lightweight, complementary approach to traditional physics-based anomaly detection methods for nuclear safeguards. In a simulated Red vs. Blue team exercise, the IFML algorithm successfully detected six significant unseen anomalies related to reactivity changes, achieving an accuracy of 99% for identifying operational deviationxs. These anomalies, caused by deliberate perturbations, were detected alongside known physics-based models, underscoring the potential of IFML to enhance real-time monitoring without displacing traditional methods. This study highlights the applicability of IFML in nuclear environments by providing an additional, redundant layer of anomaly detection to improve safeguards and operational safety in complex systems.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"211 ","pages":"Article 110990"},"PeriodicalIF":1.9,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143146588","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Numerically efficient determination of kinetic parameters of the VR-1 nuclear reactor based on experimental data and ODE-constrained optimization

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111023

Pavel Strachota , Sebastian Nývlt , Aleš Wodecki , Jan Rataj

引用次数: 0

Reduced order models for thermal hydraulic transient analysis in nuclear engineering

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111002

Young Suk Bang , Jaeseok Heo , Ha Neul Na , Kyoung-Ho Kang

{"title":"Reduced order models for thermal hydraulic transient analysis in nuclear engineering","authors":"Young Suk Bang , Jaeseok Heo , Ha Neul Na , Kyoung-Ho Kang","doi":"10.1016/j.anucene.2024.111002","DOIUrl":"10.1016/j.anucene.2024.111002","url":null,"abstract":"<div><div>Reduced order modeling emerges as a valuable tool for addressing multi-query challenges in high-fidelity computational simulations, particularly in areas such as design optimization and uncertainty analysis. Given that computational costs pose a primary obstacle to leveraging multi-physics multi-scale integrated systems, achieving computational reduction without compromising calculation accuracy through reduced order modeling offers significant advantages. This study explores two hybrid approaches to reduced order modeling, specifically applied to nuclear thermal hydraulic accident analysis. The first approach involves constructing a reduced order basis through random sampling, followed by the development of surrogate models based on linear regression, second order polynomial regression, and artificial neural network to predict time dependent thermal hydraulic behaviors. The second approach utilizes the reduced basis to transform a solution module within a thermal hydraulic analysis code, assessing the feasibility of the intrusive reduced order modeling approach. A comparison between reduced order model predictions and full order model calculations yields promising results, elucidating applicable conditions and limitations of the proposed approaches.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"211 ","pages":"Article 111002"},"PeriodicalIF":1.9,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143146560","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Negative flux fixups using positivity-preserving limiters for SN-discontinuous finite element scheme of neutron transport equation on unstructured triangular meshes

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111025

Dai Ni, Dai Tao, Xu Longfei, Qiu Youheng

{"title":"Negative flux fixups using positivity-preserving limiters for SN-discontinuous finite element scheme of neutron transport equation on unstructured triangular meshes","authors":"Dai Ni, Dai Tao, Xu Longfei, Qiu Youheng","doi":"10.1016/j.anucene.2024.111025","DOIUrl":"10.1016/j.anucene.2024.111025","url":null,"abstract":"<div><div>One significant challenge of spatial discretization for the S<em><sub>N</sub></em> transport equation is the appearance of negative solutions, resulting in numerical algorithms to be unstable or slow iterative convergence in some problems. The discontinuous Galerkin finite element (DGFEM) spatial scheme on unstructured meshes has attracted much attention in recent years, but the issue of negative solutions is still a long-standing problem. This paper studies a negative flux fixup method using positivity-preserving limiters for solving the S<em><sub>N</sub></em>-DGFEM neutron transport equation. This method uses the hierarchical basis functions and triangular reference elements to obtain arbitrary high order DGFEM scheme. In the element where appears negativities, a scaling or a rotation positivity-preserving limiter is used to scale or rotate the polynomial distribution to ensure positive solutions. Five different types of problems are selected to verify the accuracy and convergence of the method. Numerical results demonstrate that the method can produce non-negative solutions and maintain the convergence order of the original scheme, as well as not introduce too much additional computational effort.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"211 ","pages":"Article 111025"},"PeriodicalIF":1.9,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143146042","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development of mechanistic model for CHF based on boiling crisis process

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111036

Haidong Liu , Peigang Yan , Kejian Dong , Jiang Qin , Quanyao Ren , Hanzhou Liu , Deqi Chen , Hong Gao

引用次数: 0

Contribution of transient heat transfer to overpressure protection in a passive Boiling Water Reactor

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111015

Aleksandr Pomogaev, Juhani Hyvärinen, Juhani Vihavainen

{"title":"Contribution of transient heat transfer to overpressure protection in a passive Boiling Water Reactor","authors":"Aleksandr Pomogaev, Juhani Hyvärinen, Juhani Vihavainen","doi":"10.1016/j.anucene.2024.111015","DOIUrl":"10.1016/j.anucene.2024.111015","url":null,"abstract":"<div><div>The BWRX-300 reactor is a small modular reactor with 300 MW nominal electric power output. As the abbreviation indicates, the reactor is a boiling type reactor using water as the coolant. The main operating principle of the reactor model is the use of natural circulation of the coolant for both steady-state operation and emergency cooling of the reactor. Isolation Condenser Systems (ICS) have been used in early BWRs and were reintroduced in the 1990s to implement passive safety.</div><div>Modern technologies enable effective simulation of objects of various complexity. In this study, the thermal-hydraulic system code TRACE v.5 is used to simulate BWRX-300 reactor plant operation. The software enables calculation of a system consisting of the reactor pressure vessel and ICS in both steady-state and transient operation.</div><div>The ICS is an emergency cooling system borrowed from the previous generation of GE Hitachi BWRs, the ESBWRs, and it consists of a vertical tube bundle heat exchanger immersed in a water tank. Although this system design remains unchanged, its purpose is different. The BWRX-300 design completely eliminates safety and relief valves. This is why the ICS must perform both overpressure protection and long term heat dissipation functions.</div><div>Three reactor plant operation states were simulated: normal operation with nominal parameters; reactor isolation; and the transient process into the cooling down mode by reactor shutdown and ICS activation. The results demonstrate that the ICS is capable to mitigate overpressure transients. Upon ICS startup, its metallic structures absorb heat well in excess of its nominal steady-state rating. Initial thermal inertia of the system is important for overpressure mitigation in transients.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"211 ","pages":"Article 111015"},"PeriodicalIF":1.9,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143146510","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development and verification of an efficient collision algorithm for seismic analysis of fast reactor core assemblies

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.anucene.2024.111005

Shi-An Zhou , Song Yao , Bao-Ping Hei

引用次数: 0

Load-tracking performance optimization for a supercritical CO2 recompression cycle under bypass control utilizing variable turbine inlet guide vanes

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-30 DOI: 10.1016/j.anucene.2025.111230

Yadong Du, Zhiyi Yu, Ce Yang, Haimei Wang, Hanzhi Zhang

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KFK iron sphere neutron and gamma benchmark sensitivity/uncertainty analysis to n/γ nuclear data and potential use for cross section improvement

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-30 DOI: 10.1016/j.anucene.2025.111220

I. Kodeli

{"title":"KFK iron sphere neutron and gamma benchmark sensitivity/uncertainty analysis to n/γ nuclear data and potential use for cross section improvement","authors":"I. Kodeli","doi":"10.1016/j.anucene.2025.111220","DOIUrl":"10.1016/j.anucene.2025.111220","url":null,"abstract":"<div><div>The SUSD3D computer code has been recently updated with new features including the extension of the nuclear data sensitivity and uncertainty (S/U) analysis to gamma-ray quantities such as gamma flux and heating. Gamma relevant nuclear data (ENDF material files MF16, MF23, MF26) can be processed allowing S/U of coupled neutron/gamma problems. The code is available from the NEA data Bank as part of the new version of the XSUN-2023 computer code package which includes also the latest updates of the cross section and covariance matrix libraries based on the JEFF-3.3, ENDF/B-VIII.0 and FENDL-3.2 evaluations. The code was applied to the S/U analysis of the KFK neutron and γ-ray leakage benchmark to evaluate the sensitivities to iron neutron and gamma cross sections.</div><div>Sensitivity of neutron and gamma flux to the iron inelastic, elastic and capture cross sections was found to depend in an interesting way on iron shell thickness, even changing from positive to negative, which suggests that these type of measurements (in particular if repeated using more modern measurement techniques) can be powerful for the validation of iron cross sections in the high energy ranges. The need for the evaluation of gamma-ray covariances is raised.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111220"},"PeriodicalIF":1.9,"publicationDate":"2025-01-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159447","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0