Annals of Nuclear Energy最新文献_第3页

Modeling and simulating of the gas flow inside a molecular pump with different geometries by Monte Carlo method to predict the compression ratio 采用蒙特卡罗方法对不同几何形状的分子泵内部气体流动进行了建模和仿真，以预测其压缩比

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-18 DOI: 10.1016/j.anucene.2025.111391

Masoud Khajenoori , Jaber Safdari , Sadegh Yousefi-Nasab

{"title":"Modeling and simulating of the gas flow inside a molecular pump with different geometries by Monte Carlo method to predict the compression ratio","authors":"Masoud Khajenoori , Jaber Safdari , Sadegh Yousefi-Nasab","doi":"10.1016/j.anucene.2025.111391","DOIUrl":"10.1016/j.anucene.2025.111391","url":null,"abstract":"<div><div>The molecular pump is a fixed piece in the outer space of the rotor in a gas centrifuge. The molecular pump has grooves that, when moving particles collide with it, regarding the grooves are diverted in the direction that will be routed back into the rotor. One of the molecular methods for analyzing the flow of gas inside the molecular pump’s groove is the DSMC method. In this paper, while modifying the Sickafus analytical method, a trapezoidal groove of a molecular pump and a molecular pump with full geometry have been simulated using the dsmcFoam solver in OpenFOAM. The results of DSMC simulation have been compared with the results of the modified Sickafus analytical method. Also, simulation of the molecular pump with rectangular, triangular, and semi-circular geometries has been performed, and the results have been compared with the analytical method. The results show that the semicircular geometry creates the highest compression ratio during the molecular pump. Also, the results show that by improving the Sickafus analytical method, it is possible to achieve an accurate answer with a high-speed analytical method without the need to simulate the molecular pump with complex and high computing time method such as DSMC.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111391"},"PeriodicalIF":1.9,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143844186","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 and application of three-dimensional multi-physics and multi-scale coupling program for lead cooled fast reactor 铅冷快堆三维多物理场多尺度耦合程序的开发与应用

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-18 DOI: 10.1016/j.anucene.2025.111486

Sifan Dong, Jingguo Wei, Weixiang Wang, Kefan Zhang, Rui Pan, Shuai Wang, Hongli Chen

{"title":"Development and application of three-dimensional multi-physics and multi-scale coupling program for lead cooled fast reactor","authors":"Sifan Dong, Jingguo Wei, Weixiang Wang, Kefan Zhang, Rui Pan, Shuai Wang, Hongli Chen","doi":"10.1016/j.anucene.2025.111486","DOIUrl":"10.1016/j.anucene.2025.111486","url":null,"abstract":"<div><div>High-fidelity and high-precision nuclear-thermal coupling calculations for reactors can more accurately simulate the core behavior of a reactor. This work investigates the coupling of neutron physics and thermal–hydraulic behavior using the pin-by-pin subchannel thermal–hydraulic simulation code KMC-FBc based on precise geometric modeling and high-accuracy MOC (Method of Characteristics) neutron transport calculations. To examine the transient characteristics of natural circulation lead–bismuth fast reactors, this work integrates the system code RELAP5 and develops the OpenMOC/KMC-FBc/RELAP5. And the correctness of the coupling program is proved by comparing the calculation results of RELAP5. In this paper, the OpenMOC/KMC-FBc/RELAP5 coupling program is used to simulate the thermal and hydraulic phenomena under the steady state and accident conditions of the natural circulation lead cooled fast reactor (SNCLFR-100) designed by the University of Science and Technology of China. The accident conditions include unprotected transient overpower accident and unprotected loss of heat-sink accident. The results show that the OpenMOC/KMC-FBc/RELAP5 provides high accuracy and can effectively capture the physical and thermal–hydraulic variations in the reactor core under transient conditions.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111486"},"PeriodicalIF":1.9,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143844188","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

Comparison of high-fidelity transport code predictions against the NECTAR intra-pin reaction rate measurements 高保真传输码预测与NECTAR引脚内反应速率测量的比较

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-18 DOI: 10.1016/j.anucene.2025.111430

Tom Mager , Mathieu Hursin , Kyle Vaughn , Sooyoung Choi , Brendan Kochunas , Thomas Ligonnet , Vincent Lamirand , Oskari Pakari , Carlo Fiorina , Andreas Pautz

{"title":"Comparison of high-fidelity transport code predictions against the NECTAR intra-pin reaction rate measurements","authors":"Tom Mager , Mathieu Hursin , Kyle Vaughn , Sooyoung Choi , Brendan Kochunas , Thomas Ligonnet , Vincent Lamirand , Oskari Pakari , Carlo Fiorina , Andreas Pautz","doi":"10.1016/j.anucene.2025.111430","DOIUrl":"10.1016/j.anucene.2025.111430","url":null,"abstract":"<div><div>The advancement of high-fidelity nuclear reactor simulation methods is essential for reducing conservatism in safety margins and optimizing reactor design and operation. This work evaluates the predictive capabilities of the deterministic solvers GeN-Foam and MPACT for modeling intra-pin reaction rate distributions in heterogeneous reactor cores, using experimental data from the NECTAR campaign conducted at the CROCUS reactor. Radial and azimuthal reaction rate distributions from GeN-Foam and MPACT are compared to NECTAR measurements, with Serpent2 Monte Carlo simulations supporting the validation. GeN-Foam predictions align with measurements within the 0.4% experimental uncertainty, while MPACT results require further improvements to account for the 3D nature of the experiments, particularly in modeling the axial leakage in the vicinity of the dosimeter; and in the cross-section self-shielding treatment of dosimetry materials. To support broader validation efforts, this study provides detailed descriptions of the NECTAR experiments, which are planned to be integrated into the International Reactor Physics Evaluation Project (IRPhEP). Recommendations are made for future validation efforts, including additional measurements with alternative dosimeter materials and enhancements to solver methodologies.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111430"},"PeriodicalIF":1.9,"publicationDate":"2025-04-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143844187","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

Reactivity measurement using pulsed neutron source methods on VR-1 and VR-2 reactors and their verification by SERPENT code 用脉冲中子源方法测量VR-1和VR-2反应堆的反应性，并用SERPENT代码验证

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-17 DOI: 10.1016/j.anucene.2025.111432

Michal Herčík, Jan Rataj, Ondřej Huml, Filip Fejt

{"title":"Reactivity measurement using pulsed neutron source methods on VR-1 and VR-2 reactors and their verification by SERPENT code","authors":"Michal Herčík, Jan Rataj, Ondřej Huml, Filip Fejt","doi":"10.1016/j.anucene.2025.111432","DOIUrl":"10.1016/j.anucene.2025.111432","url":null,"abstract":"<div><div>A series of pulse experiments were carried out on the VR-1 reactor and the newly constructed subcritical VR-2 assembly at the Czech Technical University (CTU) in Prague. The objective was to compare the results obtained from the pulse methods with the verified Monte Carlo (Serpent) model for VR-1 reactor and to investigate the potential for the process of experimental verification of the Monte Carlo model for the new VR-2 reactor. The Simmons-King’s, Sjöstrand’s, Gozani’s, and Garelis–Russell’s methods were applied to data collected from detectors located at different positions in a pulse experiment. Additionally, the Monte Carlo method was employed for the determination of the kinetic parameters essential for the comparison and application of the pulse methods. A very simple Serpent simulation of the Sjöstrand’s method was introduced. Although the used pulse source in some of its parameters (frequency, duty factor) indicated a certain limit of applicability, the expected, relatively good agreement between the experiment and the Monte Carlo model was achieved in the investigated range of reactivities for the VR-1 reactor. Therefore, it can be concluded that pulse methods in this range provide a reasonably reliable means of determining reactivity. The discrepancies observed at the VR-2 subcritical assembly indicate the necessity for a rigorous review of its existing Monte Carlo model.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111432"},"PeriodicalIF":1.9,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143843520","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

Systematic generation of effective thermophysical and thermo-mechanical properties for reduced-order modeling of TRISO fuel pellets 系统生成有效的热物理和热机械性能，用于TRISO燃料颗粒的降阶建模

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-16 DOI: 10.1016/j.anucene.2025.111487

Samuel Heflin , Vedant Mehta , Dan Kotlyar

{"title":"Systematic generation of effective thermophysical and thermo-mechanical properties for reduced-order modeling of TRISO fuel pellets","authors":"Samuel Heflin , Vedant Mehta , Dan Kotlyar","doi":"10.1016/j.anucene.2025.111487","DOIUrl":"10.1016/j.anucene.2025.111487","url":null,"abstract":"<div><div>This work presents a detailed methodology for generating effective material properties of tri-structural isotropic (TRISO) fuel pellets for use in reduced-order homogenized thermal and/or mechanical calculations. This is achieved by use of the finite-element (FE) method to perform simulations of explicitly modeled TRISO fuel pellets, in conjunction with derivation of analytical equations for analogous homogenous pellets which preserve a particular parameter of interest. This method is applied to several properties including thermal conductivity, specific heat capacity, thermal expansion coefficient, Young’s Modulus and Poisson’s Ratio. The properties generated are a function of temperature and packing fraction. It is demonstrated that the state-of-the-art for homogenizing thermal conductivity may be inadequate for realistic TRISO pellets, while for other properties existing homogenization standards are scarce in the literature. Finally, a multi-physics application of the reduced-order properties is demonstrated, which involves coupling neutronics with thermo-mechanical calculations. The fission power distribution is obtained from neutronic analysis, and then temperature, displacement and stress–strain distributions from the explicit finite-element model are compared with those from the homogenous calculations. For the finite-element simulations, the commercial software Abaqus (<span><span>ABAQUS, 2014</span></span>) is used, and the Monte Carlo code MCNP is used for neutronics to obtain the power distributions.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111487"},"PeriodicalIF":1.9,"publicationDate":"2025-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143833913","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

Improvement of in-vessel corium transient stratification modelling regarding the uranium and zirconium phase partitioning 改进有关铀和锆相分配的腔内铈瞬态分层模型

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-15 DOI: 10.1016/j.anucene.2025.111444

J. Mativet, A. Lecoanet, R. Le Tellier

{"title":"Improvement of in-vessel corium transient stratification modelling regarding the uranium and zirconium phase partitioning","authors":"J. Mativet, A. Lecoanet, R. Le Tellier","doi":"10.1016/j.anucene.2025.111444","DOIUrl":"10.1016/j.anucene.2025.111444","url":null,"abstract":"<div><div>One of the main threats on In-Vessel Melt Retention (IVR) mitigation strategy is the transient thermochemical stratification of the liquid corium in the vessel lowerhead. This paper proposes to improve the modelling of the transient liquid phase stratification of the {U,O,Zr,Steel} system within its miscibility gap. This work is an increment on a previous model considering the metal droplet forming during the relocation, and the focus is here on improving the mass transfer modelling by treating Uranium and Zirconium separately and not as a pseudo component. This means that in the model presented here the molar ratio of Uranium over Zirconium is not equal in the oxide and in the metallic phase.</div><div>The equations of the model are presented as well as the thermodynamic closures it requires. Dissociating the transfers of Uranium and Zirconium allows for the use of thermodynamic closures that are closer to the actual thermodynamic state calculated using a Gibbs Energy minimizer.</div><div>The improved model is applied to a synthetic transient where metal is added on top of an oxide phase leading to an equilibrium state with heavy metal layer creation. This synthetic transient is further modified to reach stratification inversion. The results are compared to the previous model and show significant improvements in computing the transient stratification.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111444"},"PeriodicalIF":1.9,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828625","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

Research on sensor anomaly detection and fault location in nuclear power plants based on GAN-IAAKR model 基于GAN-IAAKR模型的核电站传感器异常检测与故障定位研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-15 DOI: 10.1016/j.anucene.2025.111462

Jiarong Gao, Yongkuo Liu, Qiang Zhao, Xin Ai, Longfei Shan

{"title":"Research on sensor anomaly detection and fault location in nuclear power plants based on GAN-IAAKR model","authors":"Jiarong Gao, Yongkuo Liu, Qiang Zhao, Xin Ai, Longfei Shan","doi":"10.1016/j.anucene.2025.111462","DOIUrl":"10.1016/j.anucene.2025.111462","url":null,"abstract":"<div><div>To address the issues of accurate anomaly detection under minor drift and accuracy degradation faults in nuclear power plant sensors, as well as the lack of data directionality, model robustness, and real-time performance in fault localization algorithms for nuclear power sensors. A GAN-IAAKR-based method for sensor anomaly detection and fault localization is proposed in this paper to accurately and promptly detect anomalous states in nuclear power plant sensors during faults and to perform fault localization for the faulty sensors First, a time-series two-dimensionalization method is employed to encode normal sensor monitoring data into images. Next, evolutionary game theory is utilized, where multiple generators and discriminators are organized into two distinct groups to simultaneously engage in the game. During the game, a replicator dynamic equation is established, and the weights of each generator and discriminator are dynamically adjusted through a smoothing mechanism. The encoded images are then fed into an enhanced GAN model for training. Building on this, the GAN model reconstructs the images, and anomaly detection is carried out by calculating the MSE statistic (reconstruction error) between the original and the reconstructed images. Finally, the improved AAKR algorithm is applied to reconstruct the sensor monitoring data. By setting a reconstruction error threshold, normal and anomalous data can be effectively differentiated, thereby enabling fault localization. Experiments were conducted to compare anomaly detection performance between One-Class SVM, Autoencoder, and GAN models under conditions of minor drift and accuracy degradation faults. The experimental results demonstrate that the proposed anomaly detection model exhibits a high detection accuracy, exceeding 95%, while the fault localization models also show superior accuracy, real-time performance, and robustness, with an accuracy rate exceeding 90%.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":""},"PeriodicalIF":1.9,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828627","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

The CoRREx neutron spectrum filtering campaign at VENUS-F for calculation-to-experiment discrepancy interpretation 金星f上的CoRREx中子谱滤波运动，用于计算与实验的差异解释

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-15 DOI: 10.1016/j.anucene.2025.111425

Federico Grimaldi , Federico Di Croce , Antonin Krása , Grégoire de Izarra , Loic Barbot , Patrick Blaise , Pierre-Etienne Labeau , Luca Fiorito , Guido Vittiglio , Jan Wagemans

{"title":"The CoRREx neutron spectrum filtering campaign at VENUS-F for calculation-to-experiment discrepancy interpretation","authors":"Federico Grimaldi , Federico Di Croce , Antonin Krása , Grégoire de Izarra , Loic Barbot , Patrick Blaise , Pierre-Etienne Labeau , Luca Fiorito , Guido Vittiglio , Jan Wagemans","doi":"10.1016/j.anucene.2025.111425","DOIUrl":"10.1016/j.anucene.2025.111425","url":null,"abstract":"<div><div>Research reactors and particularly zero power reactors serve as bridges between reactor design and deployment. The fast spectrum VENUS-F zero power reactor operated at SCK CEN has been conceived to support the development of fast heavy-metal-cooled reactor designs. Over time, several discrepancies between model results and experiments were observed, especially where the neutron spectrum is more epithermal. To identify their origin, the CoRREx experiment was conducted: B<span><math><msub><mrow></mrow><mrow><mn>4</mn></mrow></msub></math></span>C filters of different thickness were loaded in VENUS-F to investigate the relevance of the epithermal neutron spectrum to those discrepancies. We present measurements of spectral indices (fission rate ratios), <span><math><msup><mrow></mrow><mrow><mn>235</mn></mrow></msup></math></span>U fission rate traverses and reactivity worth and compare them with the results of Serpent calculations using JEFF-3.3, ENDF/B-VIII.0, ENDF/B-VIII.1 and JENDL-4.0u. CoRREx shows that the Serpent model performance in reproducing the experiment results is rather similar in the active core center and periphery. Furthermore, using B<span><math><msub><mrow></mrow><mrow><mn>4</mn></mrow></msub></math></span>C neutron spectrum filters and conducting a thorough propagation of experimental uncertainty CoRREx provides insights on the minimal contribution of the epithermal neutron flux spectrum component to the observed discrepancies. CoRREx indicates that the observed spectral index calculation-to-experiment discrepancy is attributable to the fast neutron spectrum. The Serpent model shows good performance for <span><math><msup><mrow></mrow><mrow><mn>235</mn></mrow></msup></math></span>U fission rate traverses and a slight underestimation of the filter reactivity worth.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111425"},"PeriodicalIF":1.9,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143828628","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

Experimental study on light gas transport during containment venting by using the large-scale test facility CIGMA 大型试验装置CIGMA对安全壳排气过程中轻气体输运的试验研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-15 DOI: 10.1016/j.anucene.2025.111455

Shu Soma , Masahiro Ishigaki , Yasuteru Sibamoto

{"title":"Experimental study on light gas transport during containment venting by using the large-scale test facility CIGMA","authors":"Shu Soma , Masahiro Ishigaki , Yasuteru Sibamoto","doi":"10.1016/j.anucene.2025.111455","DOIUrl":"10.1016/j.anucene.2025.111455","url":null,"abstract":"<div><div>Containment venting is one of the accident mitigation measures during severe accidents in nuclear power plants for preventing overpressure failure of the containment vessels. Because of the capability of releasing hydrogen generated in the containment vessel, the hydrogen risk can be also reduced. In this study, we conducted experiments with the large-scale test facility CIGMA to investigate the light gas transport during the venting action, mainly focusing on the effect of sump water boiling caused by the vent. The CIGMA test vessel initially pressurized by steam, air, and helium (hydrogen simulant) that formed a helium-rich density stratification was depressurized with and without sump water, with different venting flow rates, and at different venting positions. As the sump water became a steam source due to flash boiling, the helium stratification was diluted and the venting time increased twofold compared to the case without sump water, which significantly affected the amount of helium discharged to the atmosphere. Especially for the high venting flow rate condition, the amount of helium remaining in the vessel at the end of depressurization was half that of the case without sump water. Lowering the venting position from within the initial stratification to 3 m below its interface led to a threefold increase in the amount of helium remaining at the same low pressure, because of the longer time until the helium-rich stratification reached the venting position.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111455"},"PeriodicalIF":1.9,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143833912","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

A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment 用于一般生物圈评估的农作物放射性核素浓度新数学模型

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-14 DOI: 10.1016/j.anucene.2025.111447

Dongki Kim, Wontak Lee, Jonghyun Kim, Jongtae Jeong, Soonyoung Kim, Joowan Park

引用次数: 0