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Volume 53, Issue 9

Pages 2775-3126 (September 2021)

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Contents

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  1. Review Article

    1. Thermal Hydraulics

      1. Review of researches on coupled system and CFD codes

        Pages 2775-2787
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  2. Original Articles

    1. Reactor Physics

      1. Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis

        Pages 2788-2802
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      2. Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K

        Pages 2803-2815
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      3. Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

        Pages 2816-2829
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      4. Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code

        Pages 2830-2838
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    2. Thermal Hydraulics

      1. A preliminary study on material effects of critical heat flux for downward-facing flow boiling

        Pages 2839-2846
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      2. CFD analysis of the flow blockage in a rectangular fuel assembly of the IAEA 10 MW MTR research reactor

        Pages 2847-2858
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    3. Nuclear Safety

      1. Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR

        Pages 2859-2865
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      2. Experimental study of sodium fire and its characteristics under the coupling action of columnar liquid sodium flow and concrete

        Pages 2866-2877
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      3. Effect analysis of ISLOCA pathways on fission product release at Westinghouse 2-loop PWR using MELCOR

        Pages 2878-2887
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      4. Vital area identification for the physical protection of NPPs in low-power and shutdown operations

        Pages 2888-2898
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    4. Nuclear Physics, Fusion, and Laser Technology

      1. Design of online damage images detection system for large-aperture mirrors of high power laser facility based on wavefront coding technology

        Pages 2899-2908
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      2. Design of muon production target system for the RAON μSR facility in Korea

        Pages 2909-2917
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    5. Nuclear Fuel Cycle and Radioactive Waste Management

      1. Decontamination of spent ion exchange resins contaminated with iron-oxide deposits using mineral acid solutions

        Pages 2918-2925
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      2. Investigation of thorium separation from rare-earth extraction residue via electrosorption with carbon based electrode toward reducing waste volume

        Pages 2926-2936
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    6. Nuclear Fuel and Reactor Materials

      1. Thermo-mechanical coupling behavior analysis for a U–10Mo/Al monolithic fuel assembly

        Pages 2937-2952
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      2. A practical power law creep modeling of alloy 690 SG tube materials

        Pages 2953-2959
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      3. A hardening model considering grain size effect for ion-irradiated polycrystals under nanoindentation

        Pages 2960-2967
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      4. 3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms

        Pages 2968-2976
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      5. Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water

        Pages 2977-2981
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      6. Evaluation of 475 °C embrittlement in UNS S32750 super duplex stainless steel using four-point electric conductivity measurements

        Pages 2982-2989
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      7. Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes

        Pages 2990-3002
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      8. Flow-accelerated corrosion assessment for SA106 and SA335 pipes with elbows and welds

        Pages 3003-3011
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    7. Radiation Application

      1. Neutron diagnostics using nickel foil activation analysis in the KSTAR

        Pages 3012-3017
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      2. A feasibility study of using a 3D-printed tumor model scintillator to verify the energy absorbed to a tumor

        Pages 3018-3025
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    8. Radiation Protection

      1. A design of transmission-type multi-target X-ray tube based on electric field modulation

        Pages 3026-3034
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      2. A preliminary evaluation of the implementation of a radiation protection program for the lens of the eye in Korean nuclear power plants

        Pages 3035-3043
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      3. Monte Carlo approach for calculation of mass energy absorption coefficients of some amino acids

        Pages 3044-3050
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      4. Fabrication, characterization, simulation and experimental studies of the ordinary concrete reinforced with micro and nano lead oxide particles against gamma radiation

        Pages 3051-3057
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      5. Experimental investigation of zinc sodium borate glass systems containing barium oxide for gamma radiation shielding applications

        Pages 3058-3067
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    9. Nuclear Structural Analysis and Plant Management & Maintenance

      1. Damage and vibrations of nuclear power plant buildings subjected to aircraft crash part I: Model test

        Pages 3068-3084
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      2. Damage and vibrations of nuclear power plant buildings subjected to aircraft crash part II: Numerical simulations

        Pages 3085-3099
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      3. Distributed plasticity approach for nonlinear analysis of nuclear power plant equipment: Experimental and numerical studies

        Pages 3100-3111
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      4. Studies on the effect of thermal shock on crack resistance of 20MnMoNi55 steel using compact tension specimens

        Pages 3112-3121
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  3. Technical Note Nuclear Safety

    1. Signal processing method of bubble detection in sodium flow based on inverse Fourier transform to calculate energy ratio

      Pages 3122-3125
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ISSN: 1738-5733