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| 1 |
Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea
Kim, Hyun-Gil;Yang, Jae-Ho;Kim, Weon-Ju;Koo, Yang-Hyun;
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Korean Nuclear Society
, v.48, no.1, pp.1-15,
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| 2 |
Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding
Cheng, Bo;Kim, Young-Jin;Chou, Peter;
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Korean Nuclear Society
, v.48, no.1, pp.16-25,
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| 3 |
Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors
Kurata, Masaki;
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Korean Nuclear Society
, v.48, no.1, pp.26-32,
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| 4 |
A Study of Neutronics Effects of the Spacer Grids in a Typical PWR via Monte Carlo Calculation
Tran, Xuan Bach;Cho, Nam Zin;
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Korean Nuclear Society
, v.48, no.1, pp.33-42,
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| 5 |
Development of Galerkin Finite Element Method Three-dimensional Computational Code for the Multigroup Neutron Diffusion Equation with Unstructured Tetrahedron Elements
Hosseini, Seyed Abolfazl;
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Korean Nuclear Society
, v.48, no.1, pp.43-54,
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| 6 |
Sensitivity Analysis of Core Neutronic Parameters in Electron Accelerator-driven Subcritical Advanced Liquid Metal Reactor
Ebrahimkhani, Marziye;Hassanzadeh, Mostafa;Feghhi, Sayed Amier Hossian;Masti, Darush;
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Korean Nuclear Society
, v.48, no.1, pp.55-63,
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| 7 |
Precise Void Fraction Measurement in Two-phase Flows Independent of the Flow Regime Using Gamma-ray Attenuation
Nazemi, E.;Feghhi, S.A.H.;Roshani, G.H.;Gholipour Peyvandi, R.;Setayeshi, S.;
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Korean Nuclear Society
, v.48, no.1, pp.64-71,
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| 8 |
Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor
Leskovar, Matjaz;Ursic, Mitja;
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Korean Nuclear Society
, v.48, no.1, pp.72-86,
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| 9 |
A Method to Select Humane-System Interfaces for Nuclear Power Plants
Hugo, Jacques V.;Gertman, David I.;
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Korean Nuclear Society
, v.48, no.1, pp.87-97,
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| 10 |
In-situ Blockage Monitoring of Sensing Line
Mangi, Aijaz Ahmed;Shahid, Syed Salman;Mirza, Sikander Hayat;
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Korean Nuclear Society
, v.48, no.1, pp.98-113,
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| 11 |
Development of a Leading Performance Indicator from Operational Experience and Resilience in a Nuclear Power Plant
Nelson, Pamela F.;Martin-Del-Campo, Cecilia;Hallbert, Bruce;Mosleh, Ali;
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Korean Nuclear Society
, v.48, no.1, pp.114-128,
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| 12 |
Method for Inference of Operators' Thoughts from Eye Movement Data in Nuclear Power Plants
Ha, Jun Su;Byon, Young-Ji;Baek, Joonsang;Seong, Poong Hyun;
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Korean Nuclear Society
, v.48, no.1, pp.129-143,
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| 13 |
A Quantitative Team Situation Awareness Measurement Method Considering Technical and Nontechnical Skills of Teams
Yim, Ho Bin;Seong, Poong Hyun;
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Korean Nuclear Society
, v.48, no.1, pp.144-152,
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| 14 |
Measuring Situation Awareness of Operating Team in Different Main Control Room Environments of Nuclear Power Plants
Lee, Seung Woo;Kim, Ar Ryum;Park, Jinkyun;Kang, Hyun Gook;Seong, Poong Hyun;
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Korean Nuclear Society
, v.48, no.1, pp.153-163,
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| 15 |
Corrosion and Wear Properties of Cold Rolled 0.087% Gd Lean Duplex Stainless Steels for Neutron Absorbing Material
Choi, Yong;Baik, Youl;Moon, Byung-Moon;Sohn, Dong-Seong;
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Korean Nuclear Society
, v.48, no.1, pp.164-168,
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| 16 |
Evaluation of the Middle Part of the Nuclear Fuel Cycle
Kovac, Michal;
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Korean Nuclear Society
, v.48, no.1, pp.169-174,
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| 17 |
Carbon Contained Ammonium Diuranate Gel Particles Preparation in Mid-process of High-temperature Gas-cooled Reactor Fuel Fabrication
Jeong, Kyung Chai;Cho, Moon Sung;
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Korean Nuclear Society
, v.48, no.1, pp.175-181,
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| 18 |
Study on the Recycling of Nuclear Graphite after Micro-Oxidation
Liu, Juan;Wang, Chen;Dong, Limin;Liang, Tongxiang;
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Korean Nuclear Society
, v.48, no.1, pp.182-188,
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| 19 |
Design Study for Pulsed Proton Beam Generation
Kim, Han-Sung;Kwon, Hyeok-Jung;Seol, Kyung-Tae;Cho, Yong-Sub;
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Korean Nuclear Society
, v.48, no.1, pp.189-199,
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| 20 |
Characterization of a Neutron Beam Following Reconfiguration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements
Craft, Aaron E.;Hilton, Bruce A.;Papaioannou, Glen C.;
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Korean Nuclear Society
, v.48, no.1, pp.200-210,
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| 21 |
Application of Low Voltage High Resistance Grounding in Nuclear Power Plants
Chang, Choong-Koo;Hassan, Mostafa Ahmed Fouad;
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Korean Nuclear Society
, v.48, no.1, pp.211-217,
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| 22 |
Modeling of Reinforced Concrete for Reactor Cavity Analysis under Energetic Steam Explosion Condition
Kim, Seung Hyun;Chang, Yoon-Suk;Cho, Yong-Jin;Jhung, Myung Jo;
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Korean Nuclear Society
, v.48, no.1, pp.218-227,
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| 23 |
Simulation Based Investigation of Focusing Phased Array Ultrasound in Dissimilar Metal Welds
Kim, Hun-Hee;Kim, Hak-Joon;Song, Sung-Jin;Kim, Kyung-Cho;Kim, Yong-Buem;
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Korean Nuclear Society
, v.48, no.1, pp.228-235,
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| 24 |
Investigation of Burst Pressures in PWR Primary Pressure Boundary Components
Namgung, Ihn;Giang, Nguyen Hoang;
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Korean Nuclear Society
, v.48, no.1, pp.236-245,
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| 25 |
Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects
Xu, Qiang;Chen, Jianyun;Zhang, Chaobi;Li, Jing;Zhao, Chunfeng;
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Korean Nuclear Society
, v.48, no.1, pp.246-258,
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| 26 |
Nondestructive Testing of Residual Stress on the Welded Part of Butt-welded A36 Plates Using Electronic Speckle Pattern Interferometry
Kim, Kyeongsuk;Jung, Hyunchul;
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Korean Nuclear Society
, v.48, no.1, pp.259-267,
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| 27 |
PX-An Innovative Safety Concept for an Unmanned Reactor
Yi, Sung-Jae;Song, Chul-Hwa;Park, Hyun-Sik;
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Korean Nuclear Society
, v.48, no.1, pp.268-273,
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| 28 |
Spectrometry Analysis of Fumes of Mixed Nuclear Fuel (U0.8Pu0.2)O2 Samples Heated up to 2,000℃ and Evaluation of Accidental Irradiation of Living Organisms by Plutonium as the Most Radiotoxic Fission Product of Mixed Nuclear Fuel
Kim, Dmitriy;Zhumagulova, Roza;Tazhigulova, Bibinur;Zharaspayeva, Gulzhanar;Azhiyeva, Galiya;
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Korean Nuclear Society
, v.48, no.1, pp.274-284,
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