원자력 관련 해외논문. 2024

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원자력 관련 해외논문. 2024

no	논문제목	발표기관	등록일
1	Simulation of SBLOCA based on an Improved Wall Drag Partition Model for Bubbly Dispersed Flow in the RELAP5 Code	Nuclear Technology & Radiation Protection	2023-12-26
2	Development of simplified fuel assembly model for nuclear fuel transportation	Nuclear Engineering and Design	2023-11-30
3	Modeling of gamma-ray transport media in a uranium waste drum with a generative deep learning method	Radiation Measurements	2023-11-13
4	Effect of thermal properties and thickness for various metals on the Leidenfrost temperature	International Journal of Thermal Sciences	2023-10-27
5	Thermodynamic Equilibrium State Calculations for Oxidation and Corrosion Reactions of B4C and Oxide-based Neutron Absorber Compounds in Control Rods	Nuclear Engineering and Design	2023-10-18
6	Elucidating changes in the thermal creep rate of Zircaloy cladding with thin chromium coating via experiment and mechanical analysis	Surface and Coating Technology	2023-08-07
7	Improvement to the Resonance Calculation Using Energy Spectrum Expansion Method for Direct Whole-Core Calculation	M&C 2023	2023-06-16
8	GPU-accelerated Method of Characteristics with Discontinuous Galerkin Method in Unstructured Mesh Geometry	M&C 2023	2023-06-16
9	Modeling of droplet diameter changes during reflood and its application to RELAP5	CAMP(Code Application and Maintenance Program) Meeting	2023-05-23
10	Development of nuclear fuel assembly finite element model for mechanical integrity evaluation	Nuclear Engineering and Design	2023-03-30
11	Impact of oxidized HANATM and Zircaloy-4 cladding materials under high temperature on the coolability of light water reactors	Journal of Nuclear Materials	2023-03-14
12	The effect of data split on correlation errors with respect to independent validation data	NURETH-20	2023-02-03
13	Laser powder bed fusion additive manufacturing of recycled Zircaloy-4	Journal of Nuclear Materials	2022-11-30
14	A Study to Identify the Initial Conditions of Spent Nuclear Fuels for Dry Storage in Korea	International High Level Radioactive Waste Management Conference	2022-11-13
15	Application of Two-node Discontinuity Factor for Improving Accuracy of Nodal Calculation	2022 ANS Winter Meeting and Technology Expo	2022-11-13
16	Sensitivity Analysis of Heating Rate on Core Design Variables for Cobalt Target Assembly	2022 ANS Winter Meeting and Technology Expo	2022-11-13
17	Preliminary Assessment for Improved Features of KARMA Lattice Transport Code through PWR Core Follow Calculations	2022 ANS Winter Meeting and Technology Expo	2022-11-13
18	Application of Ordinary Kriging Interpolation for CPCS 3-D Power Distribution Synthesis	2022 ANS Winter Meeting and Technology Expo	2022-11-13
19	Reliability Assessment of Spent Nuclear Fuel under Normal and Accident Conditions of Longitudinal Failure Mode during Transportation	East Asia Forum on Radwaste Management (EAFORM)	2022-10-26
20	Evaluation of Control Rod Drops into Perturbed Fuel Assemblies Due to Spacer Grid Buckling	Journal of nuclear engineering and radiation science	2022-10-25
21	Effects of thermal properties and thickness for various metals on Leidenfrost temperature	International Journal of Heat and Mass Transfer	2022-10-20
22	Development of Deep Convolutional Neural Network for Prediction of Cycle Maximum Pin Power Peaking Factor in OPR1000	Annals of Nuclear Energy	2022-10-14
23	Post Irradiation Examinations of HANA-6 Cladding	2022 Topfuel	2022-10-09
24	Spent Fuel Burnup Measurement System. Evolution of SICOM-NG-FA for Republic of Korea Nuclear Power Plants	2022 Topfuel	2022-10-09
25	A New Axial Power Distribution Synthesis Method using In-Core Detector Signal and its application to Digital Core Protection System	Journal of Nuclear Science and Technology	2022-10-06
26	Effect of starting powder on microstructure and thermal conductivity of pressureless sintered fully ceramic microencapsulated fuels	Journal of European Ceramic Society	2022-08-17
27	Bayesian inference to estimate the radioactivity of three-dimensionally distributed uranium in a waste drum in a non-destructive manner	Radiation Measurements	2022-05-30
28	Modeling of droplet diameter changes during reflood	Nuclear Engineering and Design	2021-12-21
29	Modeling the effect of pre-transient and hydrogen in high-temperature steam oxidation of zirconium-based alloy using TRANOX	Journal of Nuclear Material	2021-11-09
30	The axial motion and buckling force on Hoff’s problem	ASME Journal of Applied Mechanics	2021-09-16
31	Acquisition of Fatigue Strength Reduction Factor (Kf) for Zircaloy Cladding Tube with Wear Existence	Journal of Nuclear Science and Technology	2021-08-15
32	A new quaternary additive for processing fully ceramic microencapsulated fuels without applied pressure	Journal of the European Ceramics Society	2021-07-13
33	Development a neural network model with explainable AI for measuring uranium enrichment	IEEE Transaction on Nuclear Science	2021-05-13
34	Development of the fuel assembly nonlinear model with multilinear joints	J. Pressure Vessel Technology	2021-04-09