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                             36 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A combined strategy for dynamic probabilistic risk assessment of fission battery designs using EMRALD and DEPM Earthperson, Arjun

160 C p.
artikel
2 Analysing the performance of radiological monitoring network during nuclear accidents Sangiorgi, M.

160 C p.
artikel
3 Analyzing reactor water level measurements in the Fukushima Daiichi 1 accident Sevón, Tuomo

160 C p.
artikel
4 An efficient workflow for virtual reality simulation of maintenance tasks in IFMIF-DONES Rouret, Martin

160 C p.
artikel
5 An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction Yu, Qifan

160 C p.
artikel
6 An extensive survey on radiation protection features of novel hafnium iron-borophosphate glasses: Experimental and theoretical study Şakar, Erdem

160 C p.
artikel
7 An inherently fault tolerant control of sodium cooled fast reactors and its stability analysis using particle swarm optimization T., Muthuraj

160 C p.
artikel
8 Characteristics of bubbles swimming in different liquid regions of the slug flow in vertical and inclined rectangular channel Jin, Guangyuan

160 C p.
artikel
9 CHF enhancement of CNT-COOH nanofluids in the boiling experiment with a downward-facing heating surface Wang, Shiqi

160 C p.
artikel
10 Combined impact of aging and saline solution on the swelling characteristics of compacted GMZ bentonite Sun, De'an

160 C p.
artikel
11 Defective PWR fuel rods detection and characterization using an Artificial Neural Network Verma, Lokesh

160 C p.
artikel
12 Development and validation of a general two-fluid thermal-hydraulic analysis code for reactors with plate-type fuel assemblies Xia, Jianhua

160 C p.
artikel
13 Development and verification of helium–xenon mixture cooled small reaction system Wang, Xianbo

160 C p.
artikel
14 Editorial Board
160 C p.
artikel
15 Evaluation of the operating parameters impact on hydrodynamic parameters of horizontal pulsed sieve-plate column using response surface methodology Khanramaki, Fereshte

160 C p.
artikel
16 Experimental and theoretical studies (DFT) on technetium extraction as HTcO4 using dicyclohexano-18-crown-6 in a blend of isodecyl alcohol and n-dodecane from acidic medium Khan, Pasupati Nath

160 C p.
artikel
17 Fluid retention in a tank with a horizontal positively buoyant jet Chi, Xiangyu

160 C p.
artikel
18 Homogeneous immobilization of simulated actinides in rhabdophane and comparison of its leaching stability with monazite Zheng, Qiuyu

160 C p.
artikel
19 Impact of geopolymers on hard sludge formation on the secondary side of PWR steam generators under transient conditions Fernández-Saavedra, Rocío

160 C p.
artikel
20 Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX Huang, Jinlong

160 C p.
artikel
21 In situ studies on the evolution of damage microstructures in tungsten under heavy ion irradiation and post annealing Liu, Xinyi

160 C p.
artikel
22 Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review Bhowmik, Palash K.

160 C p.
artikel
23 Integrated thermohydraulic transient testing of steam extraction loop system to support joint electricity-hydrogen production using generic boiling water reactor Smola, Tommy

160 C p.
artikel
24 Modular fuzzy control for nonlinear multipoint based core model of TMI PWR under variable fuel cycle conditions Aftab, Adnan

160 C p.
artikel
25 Monte Carlo perturbation method for optimum surface geometry due to sloshing motion Yamamoto, Toshihiro

160 C p.
artikel
26 Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis El Kheiri, Oussama

160 C p.
artikel
27 Numerical simulation of aerosol generation by cutting fuel debris and aerosol removal by spray droplets during Fukushima decommissioning Liang, Hui

160 C p.
artikel
28 Preliminary code development for single-phase liquid natural circulation flow simulation based on two-phase compressible model Dai, Jianing

160 C p.
artikel
29 Research on numerical calculation of reactor neutron noise in frequency domain and time domain Yuan, Baoxin

160 C p.
artikel
30 Semi-analytical fluid-structure model for the analysis of fuel assembly bow in full PWR cores de Lambert, Stanislas

160 C p.
artikel
31 Stability and bifurcation analysis of Generation IV reactors via point reactor models with temperature reactivity feedback Sivan, Doron

160 C p.
artikel
32 Strength and nuclear shielding performance of heavyweight concrete experimental and theoretical analysis using WinXCom program Saafan, Mohamed A.

160 C p.
artikel
33 Study on the benefit of HLLW partitioning on the high-level waste glasses from the viewpoint of waste management Wei, Meng

160 C p.
artikel
34 The research on interfacial area transport equation in rectangular channels: Experimental research and models development of sink and source terms He, Qingche

160 C p.
artikel
35 The research on the interfacial area transport equation in rectangular channels: Interfacial characteristics distribution and bubbles interaction mechanism He, Qingche

160 C p.
artikel
36 Three-dimensional thermal-hydraulic characteristics analysis of plate-type fuel reactor core based on OpenFOAM Liu, Xitong

160 C p.
artikel
                             36 gevonden resultaten
 
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