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Research on mechanism of gas leakage in microchannels of steel containment vessels for nuclear power plants Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-09 Min He, Yueyao Chen, Zhen Wu, Gangling Hou, Jialong Wang, Zhuangfei Li, Yuzhu Wang, Hanze Li
Steel containment vessels for nuclear power plants can experience gas leakage due to minute defects such as cracks, corrosion, and aging, leading to gas leakage. A gas leakage model for microchannels is established to elucidate the mechanism underlying gas leakage within microchannels caused by these defects, specifically addressing the issue of unidirectional gas flow. Computational Fluid Dynamics
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Invulnerability analysis of nuclear accidents emergency response organization network based on complex network Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-09 Wen Chen, Shuliang Zou, Changjun Qiu, Jianyong Dai, Meirong Zhang
Modern risk management philosophy emphasizes the invulnerability of human beings to cope with all kinds of emergencies. The Nuclear Accidents Emergency Response Organization (NAERO) of Nuclear Power Plant (NPP) is the primary body responsible for nuclear accidents emergency response. The invulnerability of the organization to disturbance or attack from internal and external sources is crucial in the
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Radiation tolerant capacitor-SRAM without area overhead Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-08 Eunju Jo, Hosang Yoon, Hongjoon Park, Woo-young Choi, Inyong Kwon
In memory semiconductors such as a static random access memory (SRAM), a common problem is soft errors under radiation environment. These soft errors cause bit flips, which are referred to as single event upsets (SEUs). Some radiation-hardened SRAM cells such as a Quatro SRAM, we-Quatro SRAM, and DICE SRAM cells have been reported for years. However, these designs have the disadvantage of taking up
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Experimental study of the influence of borehole parameters on prompt fission neutron uranium logging and its corrections Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-07 Pengfei Zhou, Bin Tang
In prompt fission neutron uranium logging, borehole environmental parameters affect the measured results and must be corrected. In order to explore the influence of borehole parameters on the interpretation of logging results, this paper builds a sandstone type uranium ore block model to simulate the field production drilling device based on the “Epithermal/Thermal neutron counting rate ratio” (E/T)
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Analysis of heat-loss mechanisms with various gases associated with the surface emissivity of a metal containment vessel in a water-cooled small modular reactor Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-07 Geon Hyeong Lee, Jae Hyung Park, Beomjin Jeong, Sung Joong Kim
In various small modular reactor (SMR) designs currently under development, the conventional concrete containment building has been replaced by a metal containment vessel (MCV). In these systems, the gap between the MCV and the reactor pressure vessel is filled with gas or vacuumed weakly, effectively suppressing conduction and convection heat transfer. However, thermal radiation remains the major
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New polyester composites synthesized with additions of different sized ZnO to study their shielding efficiency Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-07 M. Elsafi, M.I. Sayyed, Aljawhara H. Almuqrin
This investigation developed a novel polyester composite based on the addition of zinc oxide (ZnO) of different sizes. We prepared nine samples Containing different percentages and sizes of ZnO as well as the control sample (Pol-ZnO0). The attenuation factors of Pol-micro ZnO were estimated using Phy-x software, while the HPGe detector and various gamma sources were used to experimentally measure the
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A comparative study of different radial basis function interpolation algorithms in the reconstruction and path planning of γ radiation fields Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-07 Yulong Zhang, Jinjia Cao, Biao Zhang, Xiaochang Zheng, Wei Chen
Accurate reconstruction of radiation field and path planning are very important for the safety of operators in the process of dismantling nuclear facilities. Based on radial basis function (RBF) interpolation algorithm, this paper discussed the application of inverse multiquadric radial basis Function (IMRBF) interpolation method to the reconstruction of gamma radiation field, and proved the feasibility
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Predicting the core thermal hydraulic parameters with a gated recurrent unit model based on the soft attention mechanism Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-06 Anni Zhang, Siqi Chun, Zhoukai Cheng, Pengcheng Zhao
Accurately predicting the thermal hydraulic parameters of a transient reactor core under different working conditions is the first step toward reactor safety. Mass flow rate and temperature are important parameters of core thermal hydraulics, which have often been modeled as time series prediction problems. This study aims to achieve accurate and continuous prediction of core thermal hydraulic parameters
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Characterization of small single photon avalanche diode fabricated using standard 180 nm CMOS process for digital SiPM Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-05 Jinseok Oh, Hakcheon Jeong, Min Sun Lee, Inyong Kwon
In this work, single photon avalanche diodes (SPADs) were fabricated using the standard 180 nm complementary metal-oxide semiconductor process. Their small size of 15–16 m and low operating voltage made it possible to easily integrate them with readout circuits for compact on-chip sensors, particularly those used in the radiation sensor network of a nuclear plant. Four architectures were proposed for
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Local mechanical properties of corrosion layers formed on T91 and SS316L steels after exposure to static liquid LBE at 500 °C for 1000 h obtained by nano-indentation Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-05 Zhikun Zhou, Juan Du, Chenwen Tian, Xuhao Peng, Yabo Wu, Xi Lv, Yixiong Zhang, Ziguang Chen
Static corrosion tests in LBE under oxygen-saturated and –depleted conditions at 500 °C for 1000 h were conducted to investigate the corrosion-induced diffusion layers on T91 and SS316L steels subject to dissolution and oxidation corrosion. Following nano-indentation experiments examined the variation of local mechanical properties within the corrosion layers. Under the present conditions, T91 steel
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Failure simulation of nuclear pressure vessel under LBLOCA scenarios Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-05 Eui-Kyun Park, Jun-Won Park, Yun-Jae Kim, Kukhee Lim, Eung-Soo Kim
This paper presents the finite element deformation and failure simulation of a typical Korean high-power reactor vessel under a severe accident characterized by large break loss of coolant (LBLOCA) with in-vessel retention of molten corium through external reactor vessel cooling (IVR-ERVC) conditions. Temperature distributions calculated using Modular Accident Analysis Program Version 5 (MAAP5) as
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Waste to shield: Tailoring cordierite/mullite/zircon composites for radiation protection through controlled sintering and Y2O3 modification Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-05 Celal Avcıoğlu, Recep Artır
In this study, investment casting shell waste successfully utilized to produce cordierite/mullite/zircon composites. Green pellets, consisting of investment casting shell waste, alumina, and magnesia, were prepared and sintered at temperatures between 1250 and 1350 °C. The influence of the sintering temperature on the crystalline phase composition, densification behavior, flexural strength, microstructure
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Online analysis of iron ore slurry using PGNAA technology with artificial neural network Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-02 Haolong Huang, Pingkun Cai, Xuwen Liang, Wenbao Jia
Real-time analysis of metallic mineral grade and slurry concentration is significant for improving flotation efficiency and product quality. This study proposes an online detection method of ore slurry combining the Prompt Gamma Neutron Activation Analysis (PGNAA) technology and artificial neural network (ANN), which can provide mineral information rapidly and accurately. Firstly, a PGNAA analyzer
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A comprehensive examination of the linear and numerical stability aspects of the bubble collision model in the TRACE-1D two-fluid model applied to vertical disperse flow in a PWR core channel under loss of coolant accident conditions Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-01 Satya Prakash Saraswat, Yacine Addad
The one-dimensional Two-Fluid concept uses an area-average approach to simplify the time and phase-averaged Two-Fluid conservation equations, making it more suitable for addressing difficulties at an industrial scale. Nevertheless, the mathematical framework has inherent weaknesses due to the loss of details throughout the averaging procedures. This limitation makes the conventional model inappropriate
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Recycling and characterization of bone incorporated with concrete for gamma-radiation shielding applications Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-01 U. Rilwan, G.M. Aliyu, S.F. Olukotun, M.M. Idris, A.A. Mundi, S. Bello, I. Umar, A. El-Taher, K.A. Mahmoud, M.I. sayyed
This research intends to recycle bone and incorporate it into concrete for radiation shielding application using Phy-X/PSD software. Cement, sand and granite were mixed in proportion of 0.5 kg:1 kg:1 kg to obtain sample A. Other concretes composing of cement, sand, granite and bone ash was in proportion 0.45 kg:1 kg:1 kg:0.05 kg, 0.1 kg:1 kg:1 kg:0.4 kg and 0.35 kg:1 kg:1 kg:0.15 kg to obtain samples
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Application of data-driven model reduction techniques in reactor neutron field calculations Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-01 Zhaocai Xiang, Qiafeng Chen, Pengcheng Zhao
High-order harmonic techniques can be used to recreate neutron flux distributions in reactor cores using the neutron diffusion equation. However, traditional source iteration and source correction iteration techniques have sluggish convergence rates and protracted calculation periods. The correctness of the implicitly restarted Arnoldi method (IRAM) in resolving the eigenvalue problems of the one-dimensional
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Fault diagnosis of nuclear power plant sliding bearing-rotor systems using deep convolutional generative adversarial networks Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-03-01 Qi Li, Weiwei Zhang, Feiyu Chen, Guobing Huang, Xiaojing Wang, Weimin Yuan, Xin Xiong
Sliding bearings are crucial rotating mechanical components in nuclear power plants, and their failures can result in severe economic losses and human casualties. Deep learning provides a new approach to bearing fault diagnosis, but there is currently a lack of a universal fault diagnosis model for studying bearing-rotor systems under various operating conditions, speeds and faults. Research on bearing-rotor
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Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-29 Omar S. Al-Yahia, Ivor Clifford, Hakim Ferroukhi
Passive safety systems are integrated into the latest generation of Light Water Reactors (LWRs), including small modular reactors. This paper employs the US-NRC TRACE thermal hydraulic code to examine the performance of a passive safety condenser known as SACO, designed to serve as the ultimate heat sink for dissipating decay heat during accident scenarios. The TRACE model is constructed with reference
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Development of a dual-mode energy-resolved neutron imaging detector: High spatial resolution and large field of view Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-27 Wenqin Yang, Jianrong Zhou, Jianqing Yang, Xingfen Jiang, Jinhao Tan, Lin Zhu, Xiaojuan Zhou, Yuanguang Xia, Li Yu, Xiuku Wang, Haiyun Teng, Jiajie Li, Yongxiang Qiu, Peixun Shen, Songlin Wang, Yadong Wei, Yushou Song, Jian Zhuang, Yubin Zhao, Junrong Zhang, Zhijia Sun, Yuanbo Chen
Energy-resolved neutron imaging is an effective way to investigate the internal structure and residual stress of materials. Different sample sizes have varying requirements for the detector's imaging field of view (FOV) and spatial resolution. Therefore, a dual-mode energy-resolved neutron imaging detector was developed, which mainly consisted of a neutron scintillator screen, a mirror, imaging lenses
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Generation of LiF(Mg,Cu,Na,Si) thermoluminescent crystal and evaluation of dose response and sensitivity Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-27 Abdollah Khorshidi
In this research, thermoluminescent pellets were prepared by adding Mg, Cu, Na and Si impurities to lithium fluoride (LiF) crystal powder via melting and quenching methods to study dosimetric characteristics. Here, its reproducibility, dose response, dosimeter sensitivity, thermal and optical fading were investigated and the obtained results were compared with the properties of LiF: Cu, Mg, P crystal
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Characterization of glasses composed of PbO, ZnO, MgO, and B2O3 in terms of their structural, optical, and gamma ray shielding properties Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-26 Aljawhara H. Almuqrin, M.I. Sayyed, Ashok Kumar, U. Rilwan
The amorphous glasses containing PbO, ZnO, MgO, and BO have been fabricated using the melt quenching technique. The structural properties have been analysed using the Fourier-transform infrared (FTIR) and Raman spectroscopy. Derivative of Absorption Spectra Fitting (DASF) method have been used to estimate the band gap energy from the UV–Vis absorption data which decreases from 3.02 eV to 2.66 eV with
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Balancing the nuclear equation: Climate policy uncertainty and budgetary dynamics Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-26 Chang Li, Sajid Ali, Raima Nazar, Muhammad Saeed Meo
Amidst the uncertainties of climate policy, investing in nuclear energy technology emerges as a sustainable strategy, fostering innovation in a critical sector, while simultaneously addressing urgent environmental concerns and managing budgetary dynamics. Our investigation inspects the asymmetric influence of climate policy uncertainty on nuclear energy technology in the top 10 nations with the highest
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Influence of various metal oxides (PbO, Fe2O3, MgO, and Al2O3) on the mechanical properties and γ-ray attenuation performance of zinc barium borate glasses Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-24 Aljawhara H. Almuqrin, K.A. Mahmoud, U. Rilwan, M.I. Sayyed
The current work aims to fabricate metal oxide-doped (PbO, FeO, MgO, and AlO, each of which boasts a purity of 99%) zinc barium borate glasses through the melt quenching technique at the 1000 °C melting temperature. The results showed that adding 5 mol.% of metal oxides PbO, FeO, AlO, and MgO increases the density of the zinc barium borate glasses. Additionally, the fabricated glasses' mechanical properties
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Development and evaluation of modified lead gloves to reduce hand radiation dose during interventional radiological procedures Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-23 Hyun-Jun Park, Byungdu Jo, Seung-Jae Lee
We developed lead gloves that minimize radiation dose to the operator's hands during interventional radiological procedures and that do not impede the operator's surgical capabilities. Existing lead gloves can protect the operator's hands by shielding radiation, but use of such gloves may impair preception sensitivity, resulting in a reduction in the operator's surgical ability. Accordingly, in this
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Development of a flexible composite based on vulcanized silicon casting with bismuth oxide and characterization of its radiation shielding effectiveness in diagnostic X-ray energy range and medium gamma-ray energies Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-23 İbrahim Demirel, Haluk Yücel
The study aims to develop a novel, lead-free, flexible and lightweight composite shielding material against ionizing radiation. For this, it was used bismuth oxide (BiO) in RTV-2 silicon matrix. The shielding tests were carried out in both diagnostic X-ray energies and intermediate gamma-ray energy range of up to 662 keV to determine the radiation attenuation properties of this material in terms of
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Design of proton-beam degrader for high-purity 89Zr production Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-22 Hyunjin Lee, Sangbong Lee, Daeseong Choi, Gyoseong Jeong, Hee Seo
This work investigated the most suitable type of degrader (Cu, Al or Nb) and its thickness, taking into consideration the salient aspects of concrete activation for high-purity Zr production by Y(p,n)Zr nuclear reaction. The MCNP and FISPACT codes were used to determine the optimal degrader thickness and the radioactivity of shielding concrete by neutron activation, respectively. The results showed
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Dimensional synthesis of an Inspection Robot for SG tube-sheet Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-22 Kuan Zhang, Jizhuang Fan, Tian Xu, Yubin Liu, Zhenming Xing, Biying Xu, Jie Zhao
To ensure the operational safety of nuclear power plants, we present a Quadruped Inspection Robot that can be used for many types of steam generators. Since the Inspection Robot relies on the Holding Modules to grip the tube-sheet, it can be regarded as a hybrid robot with variable configurations, switching between 4-R-RR, 3-R-RR, and two types of 2-R-RR, and the variable configurations bring a great
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Monte Carlo simulation of spatial resolution of lens-coupled LYSO scintillator for intense pulsed gamma-ray imaging system with large field of view Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-22 Guoguang Li, Liang Sheng, Baojun Duan, Yang Li, Dongwei Hei, Qingzi Xing
In this paper, we use a Monte Carlo (MC) simulation based on Geant4 to investigate the influence of four parameters on the spatial resolution of the lens-coupled lutetium yttrium orthosilicate (LYSO) scintillator, including the thickness of the LYSO scintillator, the F-number and minification factor of the lens, and the incident position of the gamma-rays. Simulation results show that when the gamma-rays
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Laser surface cleaning of simulated radioactive contaminants in various technological environments Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-22 Maxim Cheban, Serafima Filatova, Yaroslav Kravchenko, Konstantin Scherbakov, Dmitry Mamonov, Sergey Klimentov, Maxim Savinov, Maxim Chichkov
Special methods for cleaning surfaces of stainless steel with a coating simulating radioactive contamination have been developed and studied. The removal of simulated surface contamination was performed using lasers in the micron spectral range with pulse durations of 8 ns and 270 fs. Optimal cleaning modes were determined for gas and liquid environments, achieving surface cleaning coefficient of over
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Design of an integrated multiple-single-channel analyzer Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-21 Jie Yang, Xiaofei Gu, Shuxiang Lu, Guoheng Zheng
A type of integrated multiple-single-channel analyzer (IMSCA) is described. The IMSCA works with an input pulse of 2-20 pC, and it can be directly connected to a scintillation detector, which eliminates the need for a linear amplifier. It consists of 64 input ports, so 1–64 detectors can be set by users according to different requirements. Two energy regions for each input channel can be simultaneously
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Dose absorption of Omicron variant SARS-CoV-2 by electron radiation: Using Geant4-DNA toolkit Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-19 Mehrdad Jalili Torkamani, Chiman Karami, Pooneh Sayyah-Koohi, Farhood Ziaie, Seyyedsina Moosavi, Farhad Zolfagharpour
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The influence of Ni ion addition on the microstructure and gamma ray shielding ability of ferromagnetic CuFe2O4 ceramic material Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-19 Mohammad W. Marashdeh, Fawzy H. Sallam, Ahmed M. Abd El-Aziz, Mohamed I. Elkhatib, Sitah f. Alanazi, Mamduh J. Aljaafreh, Mohannad Al-Hmoud, K.A. Mahmoud
The sintering process acquired ferromagnetic copper ferrite ceramic material with a small concentration of Ni ion at 1100 °C for 1 h. Previously, copper ferrite with Ni proportions powder was acquired by the wet chemical process according to the relation CuFeNiO where x takes values 0.0, 0.015, 0.03, 0.04, and 0.05. The role of Ni ion in the copper ferrite structure was investigated by X-ray analysis
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Radioiodine internal dose coefficients specific for Koreans Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-19 Tae-Eun Kwon, Yoonsun Chung, Choonsik Lee
This study developed internal dose coefficients for radioiodine, tailored to the Korean population, by incorporating the Korean biokinetic model along with the Korean S values. The observed differences in dose coefficients for Koreans compared to the International Commission on Radiological Protection (ICRP) reference values noticeably varied depending on physical half-lives of iodine isotopes. For
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The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-19 Qingming He, Zhanpeng Huang, Liangzhi Cao, Hongchun Wu
This paper presents two new methods for variance reduction for shielding calculation in Monte Carlo radiation transport. One method is CADIS-NEE, which combines Consistent Adjoint Driven Importance Sampling (CADIS) and next-event estimator (NEE) methods to increase the calculation efficiency of tallies at points. The other is CADIS-deterministic transport (DXTRAN), which combines CADIS and DXTRAN to
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Towards inferring reactor operations from high-level waste Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-17 Benjamin Jung, Antonio Figueroa, Malte Göttsche
Nuclear archaeology research provides scientific methods to reconstruct the operating histories of fissile material production facilities to account for past fissile material production. While it has typically focused on analyzing material in permanent reactor structures, spent fuel or high-level waste also hold information about the reactor operation. In this computational study, we explore a Bayesian
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Investigations on seismic performance of nuclear power plants equipped with an optimal BIS-TMDI considering FSI effects Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-16 Shuaijun Zhang, Gangling Hou, Chengyu Yang, Zhihua Yue, Yuzhu Wang, Min He, Lele Sun, Xuesong Cai
This paper introduces a base isolation system-tuned mass damper inerter (BIS-TMDI) hybrid system to the AP1000 nuclear power plant (NPP), which reduces seismic damage potential of the NPP structure. The effects of fluid-structure interaction (FSI) caused by the passive containment cooling system water storage tank (PCCWST) on NPP's seismic performance are investigated. The FSI of water tank theoretical
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A counting-time optimization method for artificial neural network (ANN) based gamma-ray spectroscopy Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-16 Moonhyung Cho, Jisung Hwang, Sangho Lee, Kilyoung Ko, Wonku Kim, Gyuseong Cho
With advancements in machine learning technologies, artificial neural networks (ANNs) are being widely used to improve the performance of gamma-ray spectroscopy based on NaI(Tl) scintillation detectors. Typically, the performance of ANNs is evaluated using test datasets composed of actual spectra. However, the generation of such test datasets encompassing a wide range of actual spectra representing
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Comparison of the standards for absorbed dose to water of the IAEA and the KRISS, Korea in accelerator photon beams Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-15 L. Czap, I.J. Kim, J.I. Park, C.-Y. Yi, Y. Kim, Z. Msimang
A bilateral comparison was conducted between the International Atomic Energy Agency (IAEA) and the Korea Research Institute of Standards and Science (KRISS) to measure the absorbed dose to water in accelerator photon beams. KRISS served as a linking laboratory to compare the IAEA standard with the key comparison reference value (KCRV) of the BIPM.RI(I)–K6 program, in which KRISS participated in 2017
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Does the nuclear engineering field perform worse in utilizing women? Evidence from South Korea Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-15 Jihye Kam, Sungyeol Choi, Soohyung Lee
Despite its remarkable socioeconomic development, South Korea underperforms in terms of female labor force participation and women in leadership positions. As women appear to avoid nuclear engineering, we aim to evaluate its relative performance in attracting women to its labor force compared to other college majors. Using college-major level information from 2000, we test whether the female faculty
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Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-15 Hossam H. Abdellatif, Palash K. Bhowmik, David Arcilesi, Piyush Sabharwall
The passive safety systems (PSSs) within water-cooled reactors are meticulously engineered to function autonomously, requiring no external power source or manual intervention. They depend exclusively on inherent natural forces and the fundamental principles of reactor physics, such as gravity, natural convection, and phase changes, to manage, alleviate, and avert the release of radioactive materials
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Radiation-training system with a custom survey-meter mock-up in a browser-based mixed reality environment Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-15 Hiroyuki Arakawa, Toshioh Fujibuchi, Kosuke Kaneko, Yoshihiro Okada, Toshiko Tomisawa
Training for radiation protection and control requires a visual understanding of radiation, which cannot be perceived by the human senses. Trainees must also master the effective use of measuring instruments. Traditionally, such training has exposed trainees to radiation sources. Here, we present a novel e-training strategy that enables safe, exposure-free handling of a radiation measuring tool called
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Operating condition optimization of liquid metal heat pipe using deep learning based genetic algorithm: Heat transfer performance Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-15 Ik Jae Jin, Dong Hun Lee, In Cheol Bang
Liquid metal heat pipes play a critical role in various high-temperature applications, with their optimization being pivotal to achieving optimal thermal performance. In this study, a deep learning based genetic algorithm is suggested to optimize the operating conditions of liquid metal heat pipes. The optimization performance was investigated in both single and multi-variable optimization schemes
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Neutronic optimization of thorium-based fuel configurations for minimizing slightly used nuclear fuel and radiotoxicity in small modular reactors Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-13 Nur Anis Zulaikha Kamarudin, Aznan Fazli Ismail, Mohamad Hairie Rabir, Khoo Kok Siong
Effective management of slightly used nuclear fuel (SUNF) is crucial for both technical and public acceptance reasons. SUNF management, radiotoxicity risk, and associated financial investment and technological capabilities are major concerns in nuclear power production. Reducing the volume of SUNF can simplify its management, and one possible solution is utilizing small modular reactors (SMR) and advanced
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Effects of reflector, surface treatment, and length of scintillation crystal on the performance of TOF-DOI PET detector with dual-ended readout Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-13 Jin Ho Jung, Yong Choi, Johyeon Yun, Jiwoong Jung, Sangwon Lee
The purpose of this study was to investigate the effect of the reflector, surface treatment, and length of scintillation crystals on the performance of a time-of-flight and depth-of-interaction (TOF-DOI) PET detector with a dual-ended readout and to determine the best reflector and surface treatment. Various types of crystal arrays with three different reflectors (ESR, BaSO, and Toray), three different
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Estimating North Korea's nuclear capabilities: Insights from a study on tritium production in a 5MWe graphite-moderated reactor Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-13 Sungmin Yang, Manseok Lee, Danwoo Ko, Gyunyoung Heo, Changwoo Kang, Seung Min Woo
This study explores the potential for tritium production in North Korea's 5MWe graphite-moderated reactor, a facility primarily associated with nuclear weapons material production. While existing research on these reactors has largely centered on plutonium, our focus shifts to tritium, a crucial element in boosted fission bombs. Utilizing the MCNP6 code for simulations, the results estimate that North
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Neutronic examination of the U–Mo accident tolerant fuel for VVER-1200 reactors Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-13 Semra Daydas, Ali Tiftikci
In this study, we investigated the possibility of employing accident tolerant fuel (ATF) in VVER-1200/V491 assembly without gadolinium-containing fuel rods using the Monte Carlo code Serpent 1.1.7 with ENDF/B-VII cross-section library. The analysis involves assembly design with reflective boundary conditions. To compare the neutronic performances, U–5Mo, U-7.5Mo, U–10Mo, and U–15Mo fuels were chosen
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Enhancement of critical heat flux with additive-manufactured heat-transfer surface Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-12 Tatsuya Kano, Rintaro Ono, Masahiro Furuya
In-Vessel Retention (IVR) is a key technology to retain the molten core in the reactor vessel during severe accidents of Pressurized-water reactors (PWRs). In order to gain the safety margin of IVR, it is crucial to enhance the critical heat flux (CHF) of the reactor vessel, which is submerged in a water pool. To enhance the CHF, we have designed and additive-manufactured porous grid plates with a
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A unique Vietnam's red clay-based brick reinforced with metallic wastes for γ-ray shielding purposes: Fabrication, characterization, and γ-ray attenuation properties Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-12 Ta Van Thuong, O.L. Tashlykov, K.A. Mahmoud
A unique brick series based on Vietnamese clay was manufactured at 114.22 MPa pressure rate for γ-ray attenuation purposes, consisting of (x) metallic waste & (90%-x) red clay mineral & 10% (hardener mixed with epoxy resin), where (x) is equal to the values 0%, 20%, 40%, 50%, and 70%. The impacts of industrial metal waste ratio in the structure and radiation protective characteristics were evaluated
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Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-12 Chenglong Wang, Chen Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Lead-cooled fast reactors (LFRs) have a wide range of application scenarios, which require the thermal-hydraulic characteristics of LFRs to be reliable. In the present paper, the Lead-cooled fast reactor Thermal-Hydraulic Analysis Code LETHAC was developed, including the models of pipe, heat exchanger, and pool. To verify the correctness of LETHAC, two experimental facilities and three experimental
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Impacts of Saudi Arabian fly ash on the structural, physical, and radiation shielding properties of clay bricks rich vermiculite mineral Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-10 Aljawhara H. Almuqrin, Abd Allh M. Abd El-Hamid, M.I. Sayyed, K.A. Mahmoud
The current study investigated Saudi Arabian oil fly ash impacts on Egyptian clay bricks' structural and radiation shielding properties. To produce the required bricks, crushed clay minerals from the Hafafit area were mixed with 0, 10, 20, 30, and 40 % wt.% Saudi Arabian oil fly ash and pressed at a pressure rate of 68.55 MPa. Identification of the minerals in the chosen clay was achieved via X-ray
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Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-10 Aljawhara H. Almuqrin, K.A. Mahmoud, M.I. Sayyed, H. Al-Ghamdi
The current study aims to develop new clay bricks doped with metallic waste for radiation shielding applications. The aforementioned new bricks were fabricated with various metallic waste concentrations under a pressure rate reaching ≈114 MPa and firing temperature of 1100 °C. The impacts of the metallic waste and the firing temperature on the developed brick samples' physical, radiation shielding
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Geant 4 Monte Carlo simulation for I-125 brachytherapy Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-10 Jie Liu, M.E. Medhat, A.M.M. Elsayed
This study aims to validate the dosimetric characteristics of Low Dose Rate (LDR) I-125 source Geant4-based Monte Carlo code. According to the recommendation of the American Association of Physicists in Medicine (AAPM) task group report (TG-43), the dosimetric parameters of a new brachytherapy source should be verified either experimentally or theoretically before clinical procedures.The simulation
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Advanced radiation shielding materials: PbO2-doped zirconia ceramics synthesized through innovative sol-gel method Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-10 Islam G. Alhindawy, Mohammad. W. Marashdeh, Mamduh. J. Aljaafreh, Mohannad Al-Hmoud, Sitah Alanazi, K. Mahmoud
This work demonstrates a new sol-gel approach for synthesizing PbO-doped zirconia using zircon mineral precursors. The streamlined methodology enables straightforward fabrication of the doped zirconia composites. Comprehensive materials characterization was performed using XRD, SEM, and TEM techniques to analyze the crystal structure, microstructure, and morphology. Quantitative analysis of the XRD
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Enhancement of FeCrAl-ODS steels through optimised SPS parameters and addition of novel nano-oxide formers Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-09 A. Meza, E. Macía, M. Serrano, C. Merten, U. Gaitzsch, T. Weißgärber, M. Campos
A novel approach to incorporating oxide formers into ferritic ODS production has been developed using the co-precipitation technique. This method enables the tailored design of complex nano-oxides, integrated during Mechanical Alloying (MA) and precipitated during Spark Plasma Sintering (SPS) consolidation. Findings illustrate that co-precipitation effectively produces nano-powders with customised
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Assessment of soil density and distribution coefficient of Cs-137 for deriving DCGLs in korea research reactor unit 1 and 2 Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-09 Geun-Ho Kim, Ilgook Kim, Kwang Pyo Kim
To obtain site-specific values of the Derived Concentration Guideline Levels (DCGLs) for decommissioning of KRR-1&2, the soil density and distribution coefficient values for Cs-137, a major contaminant radionuclide, were determined. The soil density was evaluated according to the test method established by the Korean Agency for Technology and Standards of the Ministry of Trade, Industry, and Energy
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Experimental study of turbulent flow in a scaled RPV model by PIV technology Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-09 Luguo Liu, Wenhai Qu, Yu Liu, Jinbiao Xiong, Songwei Li, Guangming Jiang
The turbulent flow in reactor pressure vessel (RPV) of pressurized water reactor (PWR) is important for the flow rate distribution at core inlet. Thus, it is vital to study the turbulent flow phenomena in RPV. However, the complicated fluid channel consisted of inner structures of RPV will block or refract the laser sheet of particle image velocimetry (PIV). In this work, the matched index of refraction
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Development of GPU-Paralleled multi-resolution techniques for Lagrangian-based CFD code in nuclear thermal-hydraulics and safety Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-09 Do Hyun Kim, Yelyn Ahn, Eung Soo Kim
In this study, we propose a fully parallelized adaptive particle refinement (APR) algorithm for smoothed particle hydrodynamics (SPH) to construct a stable and efficient multi-resolution computing system for nuclear safety analysis. The APR technique, widely employed by SPH research groups to adjust local particle resolutions, currently operates on a serialized algorithm. However, this serialized approach
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Experimental study on vibration projection of seawater circulation pumps in nuclear power plant Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-08 Lin Bin, Huang Qian, Zhang Rongyong, Zhu Rongsheng, Fu Qiang, Wang Xiuli
In this paper, the similarity criterion and dimensionless conversion method combined with the elasticity condition and Hooke's law are used to derive the functional relationship of the maximum effective value of the vibration velocity between the prototype pump and the model pump. The seawater circulation pump of a nuclear power plant is used as the prototype pump, and the model pump is obtained by
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Improvement of accuracy in radioactivity assessment of medical linear accelerator through self-absorption correction in HPGe detector Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-08 Suah Yu, Na Hye Kwon, Sang-Rok Kim, Young Jin Won, Kum Bae Kim, Se Byeong Lee, Cheol Ha Baek, Sang Hyoun Choi
Medical linear accelerators with an energy of 8 MV or higher are radiated owing to photonuclear reactions and neutron capture reactions. It is necessary to quantitatively evaluate the concentration of radioactive isotopes when replacing or disposing them. HPGe detectors are commonly used to identify isotopes and measure radioactivity. However, because the detection efficiency is generally calibrated
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The effect of the nozzle exit geometry on the flow characteristics of the free condensing jet Nucl. Eng. Technol. (IF 2.7) Pub Date : 2024-02-07 Jaewon Myeong, Seungwan Kim, Dehee Kim, Jongtae Kim, Weon Gyu Shin
In the present study, we investigated the velocity distribution, temperature distribution and condensation characteristics of steam jet issuing from four different orifice nozzles with a Reynolds number of approximately 79,000 using the phase Doppler particle analyzer system and a K-type thermocouple. The steam jet discharged from the orifice nozzle has a wider jet width compared to pipe nozzle because