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Volume 54, Issue 5

Pages 1535-1934 (May 2022)

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Contents

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  1. Original Articles

    1. Nuclear Fuel and Reactor Materials

      1. Overview of CSNS tantalum cladded tungsten solid Target-1 and Target-2

        Pages 1535-1540
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      2. Effective thermal conductivity model of porous polycrystalline UO2: A computational approach

        Pages 1541-1548
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      3. Study of the mechanical properties and effects of particles for oxide dispersion strengthened Zircaloy-4 via a 3D representative volume element model

        Pages 1549-1559
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      4. Effect of process parameters on the recovery of thorium tetrafluoride prepared by hydrofluorination of thorium oxide, and their optimization

        Pages 1560-1569
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      5. Creep strain modeling for alloy 690 SG tube material based on modified theta projection method

        Pages 1570-1578
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      6. Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations

        Pages 1579-1587
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      7. Prediction of fatigue crack initiation life in SA312 Type 304LN austenitic stainless steel straight pipes with notch

        Pages 1588-1596
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    2. Nuclear Fuel Cycle and Radioactive Waste Management

      1. Recovery of cesium ions from seawater using a porous silica-based ionic liquid impregnated adsorbent

        Pages 1597-1605
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      2. Novel approach to predicting the release probability when applying the MARSSIM statistical test to a survey unit with a specific residual radioactivity distribution based on Monte Carlo simulation

        Pages 1606-1615
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      3. Sorption of Se(-II) on illite, MX-80 bentonite, shale, and limestone in Na–Ca–Cl solutions

        Pages 1616-1622
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      4. Development of a gamma irradiation loop to evaluate the performance of a EURO-GANEX process

        Pages 1623-1634
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    3. Nuclear I&C

      1. A formal approach to support the identification of unsafe control actions of STPA for nuclear protection systems

        Pages 1635-1643
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      2. Adaptive second-order nonsingular terminal sliding mode power-level control for nuclear power plants

        Pages 1644-1651
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      3. Experimental testing and evaluation of coating on cables in container fire test facility

        Pages 1652-1656
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    4. Nuclear Policy, Economics and Human Resource Development

      1. Nuclear energy consumption and CO2 emissions in India: Evidence from Fourier ARDL bounds test approach

        Pages 1657-1663
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      2. Evaluating the asymmetric effects of nuclear energy on carbon emissions in Pakistan

        Pages 1664-1673
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    5. Nuclear Safety

      1. Transient simulation and experiment validation on the opening and closing process of a ball valve

        Pages 1674-1685
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      2. SACADA and HuREX: Part 1. the use of SACADA and HuREX systems to collect human reliability data

        Pages 1686-1697
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      3. Application of a combined safety approach for the evaluation of safety margin during a Loss of Condenser Vacuum event

        Pages 1698-1711
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    6. Nuclear Structural Analysis and Plant Management & Maintenance

      1. Improvement on optimal design of dynamic absorber for enhancing seismic performance of nuclear piping using adaptive Kriging method

        Pages 1712-1725
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      2. Constraint-corrected fracture mechanics analysis of nozzle crotch corners in pressurized water reactors

        Pages 1726-1746
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    7. Radiation Application

      1. Application of a deep learning algorithm to Compton imaging of radioactive point sources with a single planar CdTe pixelated detector

        Pages 1747-1753
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      2. Source and LVis based coincidence summing correction in HPGe gamma-ray spectrometry

        Pages 1754-1759
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      3. Improving light collection efficiency using partitioned light guide on pixelated scintillator-based γ-ray imager

        Pages 1760-1768
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    8. Radiation Protection

      1. Development of a dose estimation code for BNCT with GPU accelerated Monte Carlo and collapsed cone Convolution method

        Pages 1769-1780
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      2. External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1

        Pages 1781-1788
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    9. Reactor Physics

      1. Verification of a two-step code system MCS/RAST-F to fast reactor core analysis

        Pages 1789-1803
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      2. A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments

        Pages 1804-1812
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      3. Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark

        Pages 1813-1824
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    10. Thermal Hydraulics

      1. Investigation on the nonintrusive multi-fidelity reduced-order modeling for PWR rod bundles

        Pages 1825-1834
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      2. Cavitation optimization of single-orifice plate using CFD method and neighborhood cultivation genetic algorithm

        Pages 1835-1844
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      3. Can a nanofluid enhance the critical heat flux if the recirculating coolant contains debris?

        Pages 1845-1850
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      4. Experiment investigation on flow characteristics of open natural circulation system

        Pages 1851-1859
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      5. Comparative study of constitutive relations implemented in RELAP5 and TRACE – Part II: Wall boiling heat transfer

        Pages 1860-1873
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      6. Evaluation of thermal-hydraulic performance and economics of Printed Circuit Heat Exchanger (PCHE) for recuperators of Sodium-cooled Fast Reactors (SFRs) using CO2 and N2 as working fluids

        Pages 1874-1889
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      7. Development of a special thermal-hydraulic component model for the core makeup tank

        Pages 1890-1901
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  2. Technical Notes

    1. Reactor Physics

      1. Performing linear regression with responses calculated using Monte Carlo transport codes

        Pages 1902-1908
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    2. Nuclear Fuel Cycle and Radioactive Waste Management

      1. Uranium tetrafluoride production at pilot scale using a mercury electrode cell

        Pages 1909-1913
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    3. Thermal Hydraulics

      1. Numerical investigation of the critical heat flux in a 5 × 5 rod bundle with multi-grid

        Pages 1914-1928
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    4. Nuclear Fuel and Reactor Materials

      1. On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation

        Pages 1929-1934
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ISSN: 1738-5733