Digitale Bibliotheek
Sluiten Bladeren door artikelen uit een tijdschrift
     Tijdschrift beschrijving
       Alle jaargangen van het bijbehorende tijdschrift
         Alle afleveringen van het bijbehorende jaargang
                                       Alle artikelen van de bijbehorende aflevering
 
                             59 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accuracy analysis of different numerical methods on thermal stratification prediction of liquid metal Zhang, Shuai

224 C p.
artikel
2 A comprehensive depletion code MACT for molten salt reactors Zhang, Yunfei

224 C p.
artikel
3 An experimental study of dynamic debris bed remelting process in the lower head of reactor pressure vessel Jian, Lijun

224 C p.
artikel
4 A numerical stabilization model for the half-boundary method in solving heat conduction problems Yin, Haoyu

224 C p.
artikel
5 A preliminary study on activated corrosion product source term prediction in pressurized water reactor using recurrent neural network Dong, Bing

224 C p.
artikel
6 A quasi-differential measurement of neutron scattering from tantalum between 0.65 MeV and 20 MeV Siemers, Gregory J.

224 C p.
artikel
7 Assessment of radionuclide dispersion and radiation dose for a hypothetical VVER-1200 accident in Zimbabwe Chiyangwa, S.

224 C p.
artikel
8 Butterfly valve performance factors using the multiphysics object oriented simulation environment Yankura, Daniel

224 C p.
artikel
9 Comparative analysis of aerosol transport characteristics between high and low gas-liquid surface tension coefficients conditions Mei, Zhongkai

224 C p.
artikel
10 Complementary test of three-dimensional TROSE experiments for China advanced passive PWR under IVR strategy Han, Kun

224 C p.
artikel
11 Computer simulation of the processing of uranium mononitride with an argon-oxygen gas mixture Galashev, A.Y.

224 C p.
artikel
12 Decarbonizing Growth: Nuclear Energy, Green Investments, and CO₂ Emissions in BRICS Economies Xu, Yuwei

224 C p.
artikel
13 Decoupling control for pressurizer pressure and water level in nuclear power plants based on a Proportional–Integral–Derivative Neural Network Fan, Guofeng

224 C p.
artikel
14 Design of a ball screw for the electric control rod drive mechanism in nuclear reactors Qian, Chaoqun

224 C p.
artikel
15 Design of glass waste powder-reinforced ordinary concretes for gamma-ray shielding applications: An extensive experimental investigation for the physical and gamma-ray protection properties Mahmoud, K.A.

224 C p.
artikel
16 Digital twin model generation for crack propagation in steam generator tubes: Methods and implementation Jiang, Yingying

224 C p.
artikel
17 Dynamic equilibrium mechanism: Integrating small modular reactors and optimized cooling for sustainable data centers You, Zelin

224 C p.
artikel
18 Dynamic response of a freely rotating butterfly valve in the advanced test reactor − dynamic coefficients modeling Xing, Changhu

224 C p.
artikel
19 Editorial Board
224 C p.
artikel
20 Emergency evacuation model of nuclear power plant pedestrians considering emotional infection Sun, Yujie

224 C p.
artikel
21 Enhancing multi-physics modeling in new-generation nuclear reactors using machine learning: Implementing Gaussian Process Regression for updating cross sections Nasr, Mahdi Aghili

224 C p.
artikel
22 Evaluation of Aluminum Hexacyanoferrate utilization for PGM and Mo removal from simulated high-level-raffinates in reprocessing for repository area minimization Nakase, Masahiko

224 C p.
artikel
23 Experimental and analytical model study on the process of sub-cooled water jetting from high-energy pipelines Zhang, Tao

224 C p.
artikel
24 Experimental investigation of fluid flow in distorted fuel rod bundle geometry Kacz, Dániel

224 C p.
artikel
25 Fault detection and diagnosis in safety critical systems: A case study of nuclear power plants Singh, Pooja

224 C p.
artikel
26 FissionIST: A hardware-based research reactor simulator Ferreira, E.D.

224 C p.
artikel
27 Flow stability and linear disturbance analysis of single-phase natural circulation loop under different thermal boundaries Geng, Yiwa

224 C p.
artikel
28 Fuel relocation dynamics in sodium-cooled reactor transients: numerical modeling and experimental benchmarking with CABRI-LTX data Tang, Shaowei

224 C p.
artikel
29 Genetic algorithm optimization of neutron and gamma radiation shielding for neutron sources Al-Azri, Harith Mohamed

224 C p.
artikel
30 High-precision eigenvalues of the neutron transport equation by the Carlvik method Saracco, Paolo

224 C p.
artikel
31 Hydraulic stability and energy loss mechanism in main feedwater pumps of the conventional island Lu, Hongzhong

224 C p.
artikel
32 Implementation of inverse transform sampling method for photon transport in Monte Carlo code and nuclear data library preparation by NECP-Atlas Zhang, Rui

224 C p.
artikel
33 Implementation of Triply Periodic Minimal Surfaces (TPMS) as surface objects in OpenMC Ferney, Paul A.

224 C p.
artikel
34 Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE Bostelmann, Friederike

224 C p.
artikel
35 Investigating constituent redistribution in U-Zr metallic fuels: A phase-field approach incorporating porosity and sodium infiltration Jung, Woojin

224 C p.
artikel
36 KARATE-1200: An enhanced neutron transport code for VVER-1200 reactor physics calculations Hegyi, Gy.

224 C p.
artikel
37 Machine learning prediction for thermal–hydraulic parameters of semicircular-fin fuel bundle in lead–bismuth fast reactor Li, Qian

224 C p.
artikel
38 Mathematical modeling and connectivity-enhanced segmentation of void fraction in two-phase flow CT images Jiang, Zirou

224 C p.
artikel
39 Measurement uncertainty prediction of pressure tube sag measurement tool using two stage Monte Carlo simulation Hari Prasad, M.

224 C p.
artikel
40 Merging adjoint-based determinism with genetic algorithms: A hybrid approach to reactor core loading pattern optimization Abuzlf, Hadi

224 C p.
artikel
41 Neutron transmission experiment with PTFE at AKR-2 Košťál, Michal

224 C p.
artikel
42 New thorium core loading patterns for high temperature gas cooled nuclear microreactors Şentürk Lüle, Senem

224 C p.
artikel
43 Numerical study on migration behaviors of cladding melt and fuel fragment in LFR 2 × 2 rod bundle with the MPS method Yao, Peitao

224 C p.
artikel
44 Performance evaluation of a surrogate model to predict effective dose under hypothesized severe accidents of pressurized water reactor based on neural network Song, Chang Hyun

224 C p.
artikel
45 Precise implementation of the Goldstein current model for self-powered neutron detectors and comparative analysis of its approximate approaches Chen, Jun

224 C p.
artikel
46 Prediction of secondary circuit power generation for nuclear units based on WSA-VMD-BP approach Dan, Desheng

224 C p.
artikel
47 Recoating on kaolinite-based foam filters for gaseous cesium capture toward functional coating So, Byoungjin

224 C p.
artikel
48 Reliability and maintenance analysis of multi-state nuclear systems with multiple components subjected to random shocks under dynamic environments LIANG, Qingzhu

224 C p.
artikel
49 Reliability assessment of passive EHRS of IRIS based on the AM-SIS-ANN method Jiang, Hong

224 C p.
artikel
50 Research on flow and heat transfer characteristics of built-in cooling system in shaft sealed reactor coolant pump Tang, Kun

224 C p.
artikel
51 Research reactors: Global perspectives and insights into Saudi Arabia’s advancements and future prospects Shams, Afaque

224 C p.
artikel
52 Simulation and control system design of AP1000 based on APROS Luan, Tianqi

224 C p.
artikel
53 Studies of the influence of heat pipe model and coupling strategy in heat pipe microreactor simulations using Sockeye Hansel, Joshua E.

224 C p.
artikel
54 Study of the effect of burnup depth on U3Si2-Al dispersion helical cruciform fuel Li, Biao

224 C p.
artikel
55 Study on flow characteristics and formation mechanism of air-water periodic flooding in two 3 × 3 rod bundle channels Jin, Guangyuan

224 C p.
artikel
56 Study on the mechanism of temperature fluctuation induced by coaxial jets in nuclear power systems Zhou, Guo-Yan

224 C p.
artikel
57 Thermo-mechanical coupling optimization for the coolant channel design in gas-cooled microreactors Zhao, Yicheng

224 C p.
artikel
58 Unsteady flow behaviors of supercritical carbon dioxide centrifugal compressor under inlet pressure fluctuation Yang, Zimu

224 C p.
artikel
59 Utilization of thorium in accelerator driven subcritical system Du, Shijie

224 C p.
artikel
                             59 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland