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Volume 53, Issue 6

Pages 1731-2074 (June 2021)

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Contents

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  1. OriginalArticles

    1. Reactor Physics

      1. Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model

        Pages 1731-1735
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      2. Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux

        Pages 1736-1746
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      3. FAST (floating absorber for safety at transient) for the improved safety of sodium-cooled burner fast reactors

        Pages 1747-1755
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    2. Thermal Hydraulics

      1. Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle

        Pages 1756-1768
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      2. Hot and average fuel sub-channel thermal hydraulic study in a generation III+ IPWR based on neutronic simulation

        Pages 1769-1785
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      3. The optimization for the straight-channel PCHE size for supercritical CO2 Brayton cycle

        Pages 1786-1795
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      4. Prediction of critical heat flux for narrow rectangular channels in a steady state condition using machine learning

        Pages 1796-1809
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      5. Investigation of single bubble behavior under rolling motions using multiphase MPS method on GPU

        Pages 1810-1820
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      6. Experimental study on air-water countercurrent flow limitation in a vertical tube based on measurement of film thickness behavior

        Pages 1821-1833
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      7. Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth

        Pages 1834-1845
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    3. Nuclear Safety

      1. Computational mechanics and optimization-based prediction of grain orientation in anisotropic media using ultrasonic response

        Pages 1846-1857
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      2. Impact test of a centrifugal pump used in nuclear power plant under aircraft crash scenario

        Pages 1858-1868
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    4. Nuclear Fuel Cycle and Radioactive Waste Management

      1. Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel

        Pages 1869-1877
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      2. Numerical estimation of errors in drop angle during drop tests of IP-Type metallic transport containers for radioactive materials

        Pages 1878-1886
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    5. Nuclear Fuel and Reactor Materials

      1. Effect of gadolinium and boron addition on the texture development and magnetic properties of 23Cr–10NiCu duplex stainless steels

        Pages 1887-1892
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      2. A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors

        Pages 1893-1908
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      3. Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects

        Pages 1909-1923
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      4. Fracture properties and crack tip constraint quantification of 321/690 dissimilar metal girth welded joints by using miniature SENB specimens

        Pages 1924-1930
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      5. Effect of oxygen containing compounds in uranium tetrafluoride on its non-adiabatic calciothermic reduction characteristics

        Pages 1931-1938
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      6. Study on sputtering yield of tungsten with different particle sizes: Surface roughness dependence

        Pages 1939-1941
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    6. Radiation Application

      1. Study on the neutron imaging detector with high spatial resolution at China spallation neutron source

        Pages 1942-1946
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      2. Similarity analysis of pixelated CdTe semiconductor gamma camera image using a quadrant bar phantom for nuclear medicine: Monte Carlo simulation study

        Pages 1947-1954
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      3. Investigation of a novel on-site U concentration analysis method for UO2 pellets using gamma spectroscopy

        Pages 1955-1963
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      4. Measurement of TOF of fast neutrons with 238U target

        Pages 1964-1969
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      5. Optimization of target, moderator, and collimator in the accelerator-based boron neutron capture therapy system: A Monte Carlo study

        Pages 1970-1978
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    7. Radiation Protection

      1. Cohort-based evacuation time estimation using TSIS-CORSIM

        Pages 1979-1990
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      2. Indirect assessment of internal irradiation from tritium decay on Lemna Minor duckweed

        Pages 1991-1999
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      3. The influence of MgO on the radiation protection and mechanical properties of tellurite glasses

        Pages 2000-2010
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      4. Development of advanced rigorous two-step code system for evaluation of radioactive waste with high-resolution activation calculation

        Pages 2011-2018
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      5. Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process

        Pages 2019-2024
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      6. An investigation of the nuclear shielding effectiveness of some transparent glasses manufactured from natural quartz doped lead cations

        Pages 2025-2037
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    8. Nuclear Structural Analysis and Plant Management & Maintenance

      1. Development of the structural health record of containment building in nuclear power plant

        Pages 2038-2045
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    9. Nuclear Policy, Economics and Human Resource Development

      1. Identification of public concerns about radiation through a big data analysis of questions posted on a portal site in Korea

        Pages 2046-2055
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      2. An empirical investigation of nuclear energy consumption and carbon dioxide (CO2) emission in India: Bridging IPAT and EKC hypotheses

        Pages 2056-2065
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  2. Technical Note

    1. Thermal Hydraulics

      1. Energy optimization of a Sulfur–Iodine thermochemical nuclear hydrogen production cycle

        Pages 2066-2073
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ISSN: 1738-5733