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                             59 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analysis of the natural circulation system characteristics with fuel rods under motion conditions Zhang, K.

175 C p.
artikel
2 A neural-network based variable universe fuzzy control method for power and axial power distribution control of large pressurized water reactors Wan, Jiashuang

175 C p.
artikel
3 A new continuous finite element SN method for solving first-order neutron transport equation Guo, Hewei

175 C p.
artikel
4 A novel adaptive mesh free approach for even- parity neutron transport equation Alizadeh, A.

175 C p.
artikel
5 A numerical investigation into Metallic-Melt continuous drainage in the core support plate region of a BWR for the initial phase of core melt progression Okawa, Tsuyoshi

175 C p.
artikel
6 A one-dimensional model for multi-group equivalence parameters in subgroup method He, Qingming

175 C p.
artikel
7 Application of hybrid renewable energy for supplying the emergency power supply system in case of station blackout in nuclear power plant Kotb, Said A.

175 C p.
artikel
8 Application of particle swarm optimization to the reconstruction of the energy group structure for shielding library Shu, Wenyu

175 C p.
artikel
9 A preliminary study to evaluate the potential utilization of the A* search algorithm in radioactive waste storage arrangement Kastanya, Doddy

175 C p.
artikel
10 Assessing dependence in human reliability analysis using probabilistic linguistic term sets Gao, Fei

175 C p.
artikel
11 Assessment of plant response capability in the event of loss of electrical power and loss of ultimate heat sink Kim, Chang Hyun

175 C p.
artikel
12 Clearance measurement for concrete waste generated by the decommissioning of uranium processing facilities Yokoyama, Kaoru

175 C p.
artikel
13 Code development of Single-phase 2-D pressure wave propagation Gu, Zhixing

175 C p.
artikel
14 Comprehensive neutronic modeling of slug flow by Monte Carlo technique Türkmen, Mehmet

175 C p.
artikel
15 Considerations on the preliminary safety assessment for operation of the melting facility for radioactive metal waste from nuclear facilities Jeong, KwanSeong

175 C p.
artikel
16 Control system design for the once-through steam generator of lead–bismuth cooled reactor based on classical control theory Wan, Jiashuang

175 C p.
artikel
17 Coupling of first collision source method with Lattice Boltzmann Method for the solution of neutron transport equation Agarwal, Gaurav

175 C p.
artikel
18 Design and validation of a broad-group shielding library for fast reactors by using particle swarm optimization Shu, Wenyu

175 C p.
artikel
19 Development and preliminary verification of a Monte Carlo neutron transport code IMPC-Neutron Fang, Peng

175 C p.
artikel
20 Development of leak detection methods using canister surface temperature change during gas leak from canister- leak evaluation using a 1/4.5-scale cask model - Takeda, Hirofumi

175 C p.
artikel
21 Development of transient thermal-hydraulic analysis code for SCO2-cooled reactor coupled with Brayton cycle and its application Ding, H.

175 C p.
artikel
22 3-D gamma radiation field reconstruction method using limited measurements for multiple radioactive sources Zhu, Shangzhen

175 C p.
artikel
23 Dynamic mode decomposition application to dominance ratio assessment in Monte Carlo k-eigenvalue calculation Yamamoto, Toshihiro

175 C p.
artikel
24 Edge-wise perturbations to model vibrating fuel assemblies in the frequency-domain using FEMFFUSION: Development and verification Vidal-Ferràndiz, A.

175 C p.
artikel
25 Editorial Board
175 C p.
artikel
26 Experimental and analytical natural circulation analysis of the Jordanian 5 MW research reactor using plate type fuel by RELAP5 MOD3.3 Rawashdeh, Abdullah A.M.

175 C p.
artikel
27 Higher order compact finite difference schemes for steady and transient solutions of space–time neutron diffusion model Mohamed Hamada, Yasser

175 C p.
artikel
28 Improved macroscopic depletion in 2-D nodal analysis by 2x2 albedo-corrected parameterized equivalence constants method Jang, Seongdong

175 C p.
artikel
29 Modeling of neutronics and thermal-hydraulic aspects during total instantaneous blockage of central fuel subassembly in a fast reactor Narendran, Yadu

175 C p.
artikel
30 Modeling of vortex-induced vibrations for a flexible tube subjected to both internal fluid flow and external cross-flow Feng, Zhipeng

175 C p.
artikel
31 Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element Lu, Kailin

175 C p.
artikel
32 Multiphysics modeling of a critical dual-purpose canister in a saturated geological repository Swinney, Mathew W.

175 C p.
artikel
33 Neutronic and fuel cycle performance of LEU fuel with different means of excess reactivity control: Impact of neutron leakage and refueling scheme Mahbuba Nabila, Umme

175 C p.
artikel
34 Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM Ding, Wen

175 C p.
artikel
35 Numerical investigation of the depressurization performance in blowdown pipe using method of characteristics He, Xiaoqiang

175 C p.
artikel
36 Numerical solution of a comprehensive form of convection–diffusion equation for binary isotopes in the gas centrifuge Ghazanfari, Valiyollah

175 C p.
artikel
37 Numerical study of coupled slosh modes in a 3D vessel subjected to multi-directional excitations Sanapala, V.S.

175 C p.
artikel
38 Numerical study on long-term passive heat removal of EPRHR cooling water tank (CWT) using heat pipe heat exchanger Qiao, Ke

175 C p.
artikel
39 Numerical study on the effects of guide thimble on critical heat flux in a 5 × 5 fuel assembly Cong, Tenglong

175 C p.
artikel
40 Optimization analysis of HTR-PM600 fresh fuel transport container under multiple impact loading conditions Hao, Yuchen

175 C p.
artikel
41 Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating Jeong, Eun

175 C p.
artikel
42 Performance evaluation of neural network topologies for online state estimation and fault detection in pressurized water reactor Kumar, Swetha R.

175 C p.
artikel
43 Periodic magnetohydrodynamic mixed convection flow along a cone embedded in a porous medium with variable surface temperature Ashraf, Muhammad

175 C p.
artikel
44 Pressure control of Once-through steam generator using Proximal policy optimization algorithm Li, Cheng

175 C p.
artikel
45 Pre-trained network-based transfer learning: A small-sample machine learning approach to nuclear power plant classification problem Zhong, Xianping

175 C p.
artikel
46 Prioritization of radiological accident scenarios during decommissioning of nuclear power plants by risk matrix and AHP method Ok, Chi-IL

175 C p.
artikel
47 Research and Development of Source Term Activity Reconstruction System Based on Deep Learning Zhang, Gema

175 C p.
artikel
48 Research on stability characteristics of a spring-loaded valve with two outlets Jian, Jie

175 C p.
artikel
49 Review on the steam-liquid separation in the steam generator of nuclear power plants Mengyao, Wang

175 C p.
artikel
50 Signal processing applied in cortex project: From noise analysis to OMA and SSA methods Montalvo, C.

175 C p.
artikel
51 Simulation of lateral jet formation in high-speed liquid droplet impingement and its impact on crater side wall Fujisawa, Kei

175 C p.
artikel
52 Source term inversion of nuclear accident based on deep feedforward neural network Cui, Weijie

175 C p.
artikel
53 SPH simulation of natural convection in a modeled reactor core using a new combinatorial kernel Gui, Nan

175 C p.
artikel
54 Sub-channel analysis code development and core thermal calculation for fast reactor refueling cycle Sui, Danting

175 C p.
artikel
55 Three-dimensionaltransient analysis of Xi’an pulsed reactor by the coupled neutronics and thermal-hydraulics code Zhang, Xinyi

175 C p.
artikel
56 Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS Park, Hyunae

175 C p.
artikel
57 Understanding the neutron noise induced by fuel assembly vibrations in linear theory Demazière, C.

175 C p.
artikel
58 Unsteady flow behavior and two-phase region prediction in the SCO2 centrifugal compressor Bao, Wenrui

175 C p.
artikel
59 Utilization of random forest classifier and artificial neural network for predicting the acceptance of reopening decommissioned nuclear power plant Ong, Ardvin Kester S.

175 C p.
artikel
                             59 gevonden resultaten
 
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