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                             42 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A fast online procedure of background current elimination from dynamic rod worth measurement Bao, Chao

158 C p.
artikel
2 Affine reduced-order model for radiation transport problems in cylindrical coordinates Tano, Mauricio

158 C p.
artikel
3 A fourteen-tubes based semi-analytical model for fluidelastic instability threshold prediction of tube bundles in two-phase cross flow Cheng, Jianhua

158 C p.
artikel
4 A framework and a survey analysis on nuclear security culture at various radiological facilities Alrammah, Ibrahim

158 C p.
artikel
5 Algorithms of three-dimensional concrete ablation front tracking (CAFT) and crust growth Morita, Akinobu

158 C p.
artikel
6 A mesh-free treatment for even parity neutron transport equation Alizadeh, A.

158 C p.
artikel
7 An approach for performing resolved and unresolved resonance evaluation based on few or none experimental data available: Application to unstable and short-lived isotopes Leal, Luiz

158 C p.
artikel
8 A new online energy group condensation method for the high-fidelity neutronics code NECP-X Zhou, Xinyu

158 C p.
artikel
9 A novel approach for software reliability analysis of digital instrumentation and control systems in nuclear power plants Shorthill, Tate

158 C p.
artikel
10 Application of CENDL-3.2 and ENDF/B-VIII.0 on the reactor physics simulation of PWR Zu, Tiejun

158 C p.
artikel
11 Application of photofission reaction to identify high-enriched uranium by bremsstrahlung photons Chin, Kim Wei

158 C p.
artikel
12 A systematic approach to the effective strategy and plan of stakeholders for safety improvement during decommissioning of nuclear facilities Jeong, KwanSeong

158 C p.
artikel
13 Development of a method for estimating security state: Supporting integrated response to cyber-attacks in NPPs Lee, Chanyoung

158 C p.
artikel
14 Development of a new full-range critical flow model based on non-homogeneous non-equilibrium model Xu, Hong

158 C p.
artikel
15 Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: Module verification and application in CAP1400 Gao, Pengcheng

158 C p.
artikel
16 Dynamic performance investigation on the hydraulic-suspended passive shutdown subassembly of SFR Wang, Xin

158 C p.
artikel
17 Editorial Board
158 C p.
artikel
18 Ensemble learning with diversified base models for fault diagnosis in nuclear power plants Li, Jiangkuan

158 C p.
artikel
19 Experimental investigation on flow oscillation of boiling two-phase flow in a single rod channel Liu, Haidong

158 C p.
artikel
20 Experimental research on steam condensation in presence of non-condensable gas under high pressure Ma, Xizhen

158 C p.
artikel
21 Experimental study of natural circulation flow instability induced by flow boiling and loop circulation Chen, Xianbing

158 C p.
artikel
22 Experimental study on fire resistance of electrical penetration assembly (EPA) under extreme circumstances Chen, Xiaoyong

158 C p.
artikel
23 Hydrothermal-processed volcanic ash-based geopolymers for immobilization of sodium salt wastes containing Cs Liu, Li-Ke

158 C p.
artikel
24 Investigating the performance of the supervised learning algorithms for estimating NPPs parameters in combination with the different feature selection techniques Moshkbar-Bakhshayesh, Khalil

158 C p.
artikel
25 Mixed convection study on the influence of low Prandtl numbers and buoyancy in turbulent heat transfer using DNS Guo, Wentao

158 C p.
artikel
26 Neutronic performance of the hybrid-low power research reactor for education and neutron applications Kim, Kyung-O

158 C p.
artikel
27 Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments Fujimoto, Nozomu

158 C p.
artikel
28 Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor Yang, Linyi

158 C p.
artikel
29 Performance evaluation of a continuous and a discontinuous magnetic circuit annular linear induction pump Sharma, Prashant

158 C p.
artikel
30 Polynomial relaxation in the quasi-static approach and its implementation in nonlinear reactor transient analyses Oh, Tae-suk

158 C p.
artikel
31 Prediction of critical heat flux (CHF) for the high-pressure region in uniformly heated vertical round tubes Song, Meiqi

158 C p.
artikel
32 Preliminary DCGLW for surface soil of Kori Unit-1 decommissioning site according to habit data and age of human receptors Park, Se-Won

158 C p.
artikel
33 Rapid source term prediction in nuclear power plant accidents based on dynamic Bayesian networks and probabilistic risk assessment Zhao, Yunfei

158 C p.
artikel
34 Robust optimal-integral sliding mode control for a pressurized water nuclear reactor in load following mode of operation Abdulraheem, Kamal Kayode

158 C p.
artikel
35 Species transport analysis of noble metal fission product transport, deposition, and extraction in the molten salt reactor experiment Walker, Samuel A.

158 C p.
artikel
36 Stability analysis of coarse-mesh finite difference acceleration schemes and moment-based, spatially-linear discretizations Ferrer, Rodolfo M.

158 C p.
artikel
37 Studies on calculation models of ASTRA critical facility benchmark using OpenMC Zhang, Tengfei

158 C p.
artikel
38 The effect of grid generated turbulence on the fluidelastic instability response in parallel triangular tube array Akram, Muhammad Ammar

158 C p.
artikel
39 Theoretical calculation of n+235U reaction Guo, Hairui

158 C p.
artikel
40 Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with STREAM/RAST-K Jang, Jaerim

158 C p.
artikel
41 Validation of IRDFF-II library in VR-1 reactor field using thin targets Kostal, Michal

158 C p.
artikel
42 Variational nodal method for three-dimensional multigroup neutron diffusion equation based on arbitrary triangular prism Zhuang, Kun

158 C p.
artikel
                             42 gevonden resultaten
 
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