Suchergebnisse - 한국원자력학회

Mechanically-milled YBaCo4O7+ for oxygen sorbents: insights into oxygen contamination and surface structure von So, Byoungjin, Hong, Seok-Min, Lee, Chang Hwa

“… We report on the ball-milling effect and surface structure of YBaCo4O7+δ, which is being considered for use as oxygen sorbents through grazing incidence x-ray …”
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Effect of Pb, Bi and alloying elements on bonding properties and fracture toughness of FCC Fe grain boundary von Liang Wenyan, Wen Rumeng, Liu Zhe, Yang Lingyun, Sun Lei, Gong Xing, Liang Chaoping

“… In accelerator-driven nuclear systems, the compatibility of liquid lead-bismuth eutectic (LBE) with austenitic (FCC Fe based) stainless steel is critical. This …”
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Distribution coefficients K of cobalt ions in soil samples of Anarak near-surface radioactive waste repository studied by batch and three different column methods von Esmaeiliboosjin, Maliheh, Aminisisakht, Marzieh, Poursharifiravari, Mohadeseh, Dara, Mojtaba, Samadfam, Mohammad

“… The selection of appropriate transport parameters of radionuclides is of utmost importance in the safety assessment of radioactive waste disposal sites. Both …”
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A method to obtain radioactivity of non- nuclides by 60Co based on Monte Carlo simulations von Shi Yingbo, Xiang Yulin, Su Rongbo, Hu Bitao, Sun Shaohua, Liu Zuoye

“… Source term investigation is a critically important aspect of reactor decommissioning, particularly as the range of nuclides under consideration expands beyond …”
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Application of CFD model for Passive Autocatalytic Recombiners to formulate an empirical correlation for integratral containment analysis von Shukla Vikram, Gera Bhuvaneshwar, Ganju Sunil, Varma Salil, Maheshwari N.K., Guchhait P.K., Sengupta S.

“… Hydrogen mitigation using Passive Autocatalytic Recombiners (PARs) has been widely accepted methodology inside reactor containment of accident struck Nuclear …”
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Thickness evaluation of Cr coating fuel rod using encircle ECT sensor von 박정원, 하종문, 승홍민, 장훈(한전원자력연료, 최원재

“… To improve the safety and life extension qualities of nuclear fuel rods which is currently made of zirconium (Zr) alloy, research on the application of …”
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Evaluation of cadmium ratio for conceptual design of a cyclotronbased thermal neutron radiography system von Weng-Sheng Kuo

“… An approximate method for calculating the cadmium ratio of a cyclotron-based thermal neutron radiography system was developed. In this method, the Monte-Carlo …”
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Corrosion behavior and mechanism of CLAM and 316L steels in fl owing Pb – 17Li alloy under magnetic field von Zunqi Xiao, Jing Liu, Zhizhong Jiang, Lin Luo, Qunying Huang

“… The liquid lead-lithium (Pbe17Li) blanket has many applications in fusion reactors due to its good tritiumbreeding performance, high heat transfer efficiency …”
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Conceptual design of a copper-bonded steam generator for SFR and the development of its thermalhydraulic analyzing code von 임성혁, 정요한, 홍종간, 최선락

“… The Korea Atomic Energy Research Institute (KAERI) studied the sodium-water reaction (SWR) minimized steam generator for the safety of the sodium-cooled fast …”
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Uncertainty quantifi cation of the power control system of a small PWR with coolant temperature perturbation von Xiaoyu Li, Chuhao Li, Yang Hu, Yongqi Yu, Wenjie Zeng, Haibiao Wu

“… The coolant temperature feedback coefficient is an important parameter of reactor core power controlsystem. To study the coolant temperature feedback …”
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Physical protection system vulnerability assessment of a small nuclear research reactor due to TNTshaped charge impact on its reinforced concrete wall von 무지훈, Sunil S. Chirayath, 조성국(이노스기술

“… A nuclear energy facility is one of the most critical facilities to be safely protected during and afteroperation because the physical destruction of its …”
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An improved regularized particle fi lter for remaining useful life prediction in nuclear plant electric gate valves von Ren-yi Xu, Hang Wang, Min-jun Peng, Yong-kuo Liu

“… Accurate remaining useful life (RUL) prediction for critical components of nuclear power equipment is animportant way to realize aging management of nuclear …”
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Graded approach to determine the frequency and diffi culty of safety culture attributes: The F-D matrix von 안지예, 민병주, 이승준

“… The importance of safety culture has been emphasized to achieve a high level of safety. In this light, asystematic method to more properly deal with safety …”
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Multi-channel analyzer based on a novel pulse fi tting analysis method von Qingshan Wang(Engineering Research Center of Nuclear Technology Application, Xiongjie Zhang(Engineering Research Center of Nuclear Technology Application, Xiangting Meng(Engineering Research Center of Nuclear Technology Application, Bao Wang(Engineering Research Center of Nuclear Technology Application, Dongyang Wang(Engineering Research Center of Nuclear Technology Application, Pengfei Zhou(Engineering Research Center of Nuclear Technology Application, Renbo Wang(Engineering Research Center of Nuclear Technology Application, Bin Tang(Engineering Research Center of Nuclear Technology Application

“… A novel pulse fitting analysis (PFA) method is presented for the acquisition of nuclear spectra. Thecharging process of the feedback capacitor in the resistive …”
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Effect of process parameters on the recovery of thorium tetrafl uoride prepared by hydrofl uorination of thorium oxide, and their optimization von Raj Kumar, Sonal Gupta, Sourabh Wajhal, S.K. Satpati, M.L. Sahu

“… Liquid fueled molten salt reactors (MSRs) have seen renewed interest because of their inherent safetyfeatures, higher thermal efficiency and potential for …”
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Numerical investigation of the critical heat fl ux in a 5 × 5 rod bundle with multi-grid von Wei Liu, Zemin Shang, Shihao Yang, Lixin Yang, Zihao Tian, Yu Liu, Xi Chen, Qian Peng

“… To improve the heat transfer efficiency of the reactor fuel assembly, it is necessary to accurately calculatethe two-phase flow boiling characteristics and the …”
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Verification of SARAX code system in the reactor core transient calculation based on the simplifi ed EBRII benchmark von Xiaoqian Jia, Youqi Zheng, Xianna Du, Yongping Wang, Jianda Chen

“… This paper shows the verification work of SARAX code system in the reactor core transient calculationbased on the simplified EBR-II Benchmark. The SARAX code …”
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Evaluation of thermal-hydraulic performance and economics of Printed Circuit Heat Exchanger (PCHE) for recuperators of Sodium-cooled Fast Reactors (SFRs) using CO 2 and N 2 as working fluids von 이수원, 신성민, 정성균, 조항진

“… In this study, we evaluate the thermal-hydraulic performance and economics of Printed Circuit HeatExchanger (PCHE) according to the channel types and …”
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Effective thermal conductivity model of porous polycrystalline UO 2 : A computational approach von 윤보현(경희대학교, 장근옥

“… The thermal conductivity of uranium oxide (UO2) containing pores and grain boundaries is investigatedusing continuum-level simulations based on the …”
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A formal approach to support the identifi cation of unsafe control actions of STPA for nuclear protection systems von 정세진, 허윤아, 유준범

“… STPA (System-Theoretic Process Analysis) is a widely used safety analysis technique to identify UCAs(Unsafe Control Actions) resulting in potential losses. It …”
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