nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
|
Khvostov, G. |
|
|
52 |
12 |
p. 2887-2900 |
artikel |
2 |
Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library
|
Hartanto, Donny |
|
|
52 |
12 |
p. 2725-2732 |
artikel |
3 |
Analytic responses of slender beams supported by rotationally restrained hinges during support motions
|
Ryu, Jeong Yeon |
|
|
52 |
12 |
p. 2939-2948 |
artikel |
4 |
Analyzing local perceptions toward the new nuclear research reactor in Thailand
|
Tantitaechochart, Sarasinee |
|
|
52 |
12 |
p. 2958-2968 |
artikel |
5 |
An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis
|
Lin, Ching-Sheng |
|
|
52 |
12 |
p. 2733-2742 |
artikel |
6 |
A new perspective towards the development of robust data-driven intrusion detection for industrial control systems
|
Ayodeji, Abiodun |
|
|
52 |
12 |
p. 2687-2698 |
artikel |
7 |
Application of deep neural networks for high-dimensional large BWR core neutronics
|
Abu Saleem, Rabie |
|
|
52 |
12 |
p. 2709-2716 |
artikel |
8 |
Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon
|
Jha, Alok |
|
|
52 |
12 |
p. 2760-2770 |
artikel |
9 |
CFD study of the PTS experiment in ROCOM test facility
|
Čarija, Zoran |
|
|
52 |
12 |
p. 2803-2811 |
artikel |
10 |
Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor
|
Zhao, Pengcheng |
|
|
52 |
12 |
p. 2789-2802 |
artikel |
11 |
Comprehensive validation of silicon cross sections
|
Czakoj, Tomáš |
|
|
52 |
12 |
p. 2717-2724 |
artikel |
12 |
Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code
|
Kim, Mun Soo |
|
|
52 |
12 |
p. 2743-2759 |
artikel |
13 |
Crack growth analysis and remaining life prediction of dissimilar metal pipe weld joint with circumferential crack under cyclic loading
|
Murthy, A. Ramachandra |
|
|
52 |
12 |
p. 2949-2957 |
artikel |
14 |
Effects of house load operation on PSA based on operational experiences in Korea
|
Lim, Hak Kyu |
|
|
52 |
12 |
p. 2812-2820 |
artikel |
15 |
Entropy and exergy analysis and optimization of the VVER nuclear power plant with a capacity of 1000 MW using the firefly optimization algorithm
|
Talebi, Saeed |
|
|
52 |
12 |
p. 2928-2938 |
artikel |
16 |
Evaluation of the radiation damage effect on mechanical properties in Tehran research reactor (TRR) clad
|
Amirkhani, Mohamad Amin |
|
|
52 |
12 |
p. 2975-2981 |
artikel |
17 |
Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution
|
Al-Yahia, Omar S. |
|
|
52 |
12 |
p. 2771-2788 |
artikel |
18 |
Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model
|
Kim, Yeon Soo |
|
|
52 |
12 |
p. 2836-2846 |
artikel |
19 |
Is nuclear energy a better alternative for mitigating CO2 emissions in BRICS countries? An empirical analysis
|
Hassan, Syed Tauseef |
|
|
52 |
12 |
p. 2969-2974 |
artikel |
20 |
Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation
|
Ding, Xiao-Yu |
|
|
52 |
12 |
p. 2860-2866 |
artikel |
21 |
Novel homogeneous burnable poisons in pressurized water reactor ceramic fuel
|
Dodd, Brandon |
|
|
52 |
12 |
p. 2874-2879 |
artikel |
22 |
On-site water level measurement method based on wavelength division multiplexing for harsh environments in nuclear power plants
|
Lee, Hoon-Keun |
|
|
52 |
12 |
p. 2847-2851 |
artikel |
23 |
Parameter importance ranking for SBLOCA of CPR1000 with moment-independent sensitivity analysis
|
Xiong, Qingwen |
|
|
52 |
12 |
p. 2821-2835 |
artikel |
24 |
Performance of 3D printed plastic scintillators for gamma-ray detection
|
Kim, Dong-geon |
|
|
52 |
12 |
p. 2910-2917 |
artikel |
25 |
Restoration of the isotopic composition of reprocessed uranium hexafluoride using cascade with additional product
|
Palkin, Valerii |
|
|
52 |
12 |
p. 2867-2873 |
artikel |
26 |
Simplified elastic-plastic analysis procedure for strain-based fatigue assessment of nuclear safety class 1 components under severe seismic loads
|
Kim, Jong-Sung |
|
|
52 |
12 |
p. 2918-2927 |
artikel |
27 |
Simulation, design optimization, and experimental validation of a silver SPND for neutron flux mapping in the Tehran MTR
|
Saghafi, Mahdi |
|
|
52 |
12 |
p. 2852-2859 |
artikel |
28 |
Technical Reviewers 2020
|
|
|
|
52 |
12 |
p. I-XXII |
artikel |
29 |
Thermal creep behavior of CZ cladding under biaxial stress state
|
Xin, Jin |
|
|
52 |
12 |
p. 2901-2909 |
artikel |
30 |
Thermodynamic and experimental analyses of the oxidation behavior of UO2 pellets in damaged fuel rods of pressurized water reactors
|
Jung, Tae-Sik |
|
|
52 |
12 |
p. 2880-2886 |
artikel |
31 |
Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator
|
Abdelhameed, Ahmed Amin E. |
|
|
52 |
12 |
p. 2699-2708 |
artikel |