| no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
| 1 |
ACE surrogate Model–Based uncertainty and sensitivity analysis methods for severe accident codes
|
Ahn, Kwang-Il
|
|
|
56 |
9 |
p. 3686-3699
|
article
|
| 2 |
An efficient numerical modeling approach for coupled electrical cabinets in nuclear power plants
|
Turja, Sudeep Das
|
|
|
56 |
9 |
p. 3512-3527
|
article
|
| 3 |
A new surrogate method for the neutron kinetics calculation of nuclear reactor core transients
|
Li, Xiaoqi
|
|
|
56 |
9 |
p. 3571-3584
|
article
|
| 4 |
Assessment of environmental fatigue in nuclear power plants: A comparative analysis of the effects of plasticity correction
|
Han, Tae-Song
|
|
|
56 |
9 |
p. 3764-3774
|
article
|
| 5 |
A study on modeling of boiling heat transfer in core debris bed of SFR
|
Venkateswarlu, S.
|
|
|
56 |
9 |
p. 3864-3871
|
article
|
| 6 |
Conceptual design for a 5 kWe space nuclear reactor power system
|
Mei, Huaping
|
|
|
56 |
9 |
p. 3644-3653
|
article
|
| 7 |
Conceptual RF design of 750 MHz IH cavities for β = 0.10–0.15 ion beams in medical accelerators
|
Giner Navarro, Jorge
|
|
|
56 |
9 |
p. 3536-3544
|
article
|
| 8 |
Corrigendum to “Preliminary study of artificial intelligence-based fuel-rod pattern analysis of low-quality tomographic image of fuel assembly” [Nucl. Eng. Technol. 54 (10) (2022) 3943–3948]
|
Sung, Saerom
|
|
|
56 |
9 |
p. 3981
|
article
|
| 9 |
Coupled 3D thermal-hydraulic code development for performance assessment of spent nuclear fuel disposal system
|
Park, Samuel
|
|
|
56 |
9 |
p. 3950-3960
|
article
|
| 10 |
Discharge characterization of two-region arc plasma (TRAP) ion source
|
Lee, Kihyun
|
|
|
56 |
9 |
p. 3961-3968
|
article
|
| 11 |
Effect of supplementary cementitious materials on the degradation of cement-based barriers in radioactive waste repository: A case study in Korea
|
Kim, Min-Seok
|
|
|
56 |
9 |
p. 3942-3949
|
article
|
| 12 |
Effects of microalloying element addition on mechanical properties of SA508 Gr.1A low-alloy steels
|
Hyun, Se-mi
|
|
|
56 |
9 |
p. 3528-3535
|
article
|
| 13 |
Enhancing X-ray radiation protection with novel liquid silicone rubber composites: A promising alternative to lead aprons
|
Abdullah, Wesam
|
|
|
56 |
9 |
p. 3608-3615
|
article
|
| 14 |
Evaluating polyester resin as a viable substitute for PMMA in computed tomography dosimetry phantoms
|
Khallouqi, A.
|
|
|
56 |
9 |
p. 3758-3763
|
article
|
| 15 |
Extended cognitive reliability and error analysis method for advanced control rooms of nuclear power plants
|
Zhang, Xiaodan
|
|
|
56 |
9 |
p. 3472-3482
|
article
|
| 16 |
Extensive analysis of several Indian and Yemeni soils' gamma-ray shielding characteristics: An experimental and simulation approach
|
Obaid, Shamsan S.
|
|
|
56 |
9 |
p. 3558-3565
|
article
|
| 17 |
Fission counter array for pulse-mode measurements of high-flux and high-energy neutrons
|
Lee, Pilsoo
|
|
|
56 |
9 |
p. 3553-3557
|
article
|
| 18 |
Fission source convergence diagnosis in Monte Carlo eigenvalue calculations by skewness and kurtosis estimation methods
|
Park, Ho Jin
|
|
|
56 |
9 |
p. 3775-3784
|
article
|
| 19 |
Flow-induced vibrations of dual-cylinders in axial flow via LES simulations
|
Shi, Kangfei
|
|
|
56 |
9 |
p. 3812-3825
|
article
|
| 20 |
Generation of security system defense strategies based on evolutionary game theory
|
Zou, Bowen
|
|
|
56 |
9 |
p. 3463-3471
|
article
|
| 21 |
High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup
|
Kim, Taeil
|
|
|
56 |
9 |
p. 3700-3716
|
article
|
| 22 |
Hybrid vibro-acoustic model reduction for model updating in nuclear power plant pipeline with undetermined boundary conditions
|
Shin, Hyeonah
|
|
|
56 |
9 |
p. 3491-3500
|
article
|
| 23 |
Identification of primary input parameters affecting evacuation in ventilated main control room through CFAST simulations and application of a machine learning algorithm to replace CFAST model
|
Singh, Sumit Kumar
|
|
|
56 |
9 |
p. 3717-3729
|
article
|
| 24 |
Impact of fuel temperature on nuclear core design calculations
|
Čalič, Dušan
|
|
|
56 |
9 |
p. 3668-3685
|
article
|
| 25 |
Implementation of dynamic start-up test experimental data as a main part of the nuclear code validation procedure: Developed RELAP5 model for VVER-1000
|
Vahman, Navid
|
|
|
56 |
9 |
p. 3826-3834
|
article
|
| 26 |
Improved FMM for well locations optimization in in-situ leaching areas of sandstone uranium mines
|
Jia, Mingtao
|
|
|
56 |
9 |
p. 3750-3757
|
article
|
| 27 |
Improvement of internal exposure assessments of the inhalation of fuel-type hot particles during long-term outages
|
Cho, Moonhyung
|
|
|
56 |
9 |
p. 3925-3932
|
article
|
| 28 |
Life prediction of IGBT module for nuclear power plant rod position indicating and rod control system based on SDAE-LSTM
|
Chen, Zhi
|
|
|
56 |
9 |
p. 3740-3749
|
article
|
| 29 |
Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor
|
Mishra, Vaibhav
|
|
|
56 |
9 |
p. 3969-3980
|
article
|
| 30 |
Method of the known cross sections for calibration of the fast neutron spectrometer with a single-crystal stilbene based detector
|
Urupa, I.V.
|
|
|
56 |
9 |
p. 3602-3607
|
article
|
| 31 |
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
|
Cui, Tongyan
|
|
|
56 |
9 |
p. 3545-3552
|
article
|
| 32 |
Noticeable localized corrosion of solid boric acid on 304 stainless steel
|
Li, Xinzhu
|
|
|
56 |
9 |
p. 3616-3625
|
article
|
| 33 |
Optimization method for offsite consequence analysis by efficient plume segmentation
|
Kim, Seunghwan
|
|
|
56 |
9 |
p. 3851-3863
|
article
|
| 34 |
Optimizing irradiation conditions for natural molybdenum in WWR-K reactor
|
Sairanbayev, D.S.
|
|
|
56 |
9 |
p. 3566-3570
|
article
|
| 35 |
Pebble flow in the HTR-PM reactor core by GPU-DEM simulation: Effect of friction
|
Zhang, Zuoyi
|
|
|
56 |
9 |
p. 3835-3850
|
article
|
| 36 |
Prediction of small-scale leak flow rate in LOCA situations using bidirectional GRU
|
Jo, Hye Seon
|
|
|
56 |
9 |
p. 3594-3601
|
article
|
| 37 |
Pulse pile-up correction by auto-regression on linear operations (ARLO) method: A comparison with integration-based algorithms
|
Mohammadian-Behbahani, Mohammad-Reza
|
|
|
56 |
9 |
p. 3904-3913
|
article
|
| 38 |
Real-time measurements and modeling of sodium combustion aerosol dynamics in test chamber to improve the evaluation of SFR containment aerosol behaviour
|
Pujala, Usha
|
|
|
56 |
9 |
p. 3483-3490
|
article
|
| 39 |
Solution of OECD/NEA PWR MOX/UO2 benchmark with a high-performance pin-by-pin core calculation code
|
Hong, Hyunsik
|
|
|
56 |
9 |
p. 3654-3667
|
article
|
| 40 |
Source term inversion of nuclear accidents based on ISAO-SAELM model
|
Xiao, Dong
|
|
|
56 |
9 |
p. 3914-3924
|
article
|
| 41 |
Structural, physical, optical, and gamma ray shielding properties of SnO2-based boro-silicate glasses: The influence of substituting Na2O by SnO2
|
Marashdeh, Mohammad W.
|
|
|
56 |
9 |
p. 3804-3811
|
article
|
| 42 |
Studies on structural, optical, thermal and low energy shielding for gamma rays for the ZSBP glasses
|
Altowyan, Abeer S.
|
|
|
56 |
9 |
p. 3796-3803
|
article
|
| 43 |
Study on producing radioisotopes based on fission or radiative capture method in a high flux reactor
|
Xu, Wei
|
|
|
56 |
9 |
p. 3585-3593
|
article
|
| 44 |
Study on the behavior of radionuclides in geologic samples from fault zone, Gabal Um Hamd, southwestern Sinai, Egypt
|
El Afandy, Doaa M.
|
|
|
56 |
9 |
p. 3785-3795
|
article
|
| 45 |
Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrity
|
Shen, Xing-Chao
|
|
|
56 |
9 |
p. 3730-3739
|
article
|
| 46 |
The effect of zinc, iron and manganese content on gamma shielding properties of magnesium-based alloys produced using the powder metallurgy
|
Ekici, Mesut Ramazan
|
|
|
56 |
9 |
p. 3872-3883
|
article
|
| 47 |
The radioactivity levels and beta dose rate assessment from dental ceramic materials in Egypt
|
Hasabelnaby, Mohamed
|
|
|
56 |
9 |
p. 3898-3903
|
article
|
| 48 |
The study and design of a deuteron drift tube linear accelerator for middle energy neutron source
|
Wei, Tianhao
|
|
|
56 |
9 |
p. 3933-3941
|
article
|
| 49 |
Titanium alloys: A closer-look at mechanical, gamma-ray, neutron, and transmission properties of different grade alloys through MCNPcode application
|
ALMisned, Ghada
|
|
|
56 |
9 |
p. 3501-3511
|
article
|
| 50 |
Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel
|
Jo, YuGwon
|
|
|
56 |
9 |
p. 3626-3643
|
article
|
| 51 |
Understanding the creep behavior of bentonite-sand mixtures as buffer materials in a low-level radioactive waste repository in Taiwan
|
Ren, Guo-Liang
|
|
|
56 |
9 |
p. 3884-3897
|
article
|
Journal description