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                             42 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A boron-adjustment-free control strategy for large pressurized water reactors Wan, Jiashuang

174 C p.
artikel
2 Analysis and enhancements of the coolant velocity estimation method in PWR core Kiss, Sándor

174 C p.
artikel
3 Analysis for the use of thorium based fuel in LWRs Raj, Devesh

174 C p.
artikel
4 Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors Ványi, A. Sz.

174 C p.
artikel
5 A new coupling method based on MOC and the SN nodal method for the neutron transport calculations Liu, Zhouyu

174 C p.
artikel
6 An intelligent multi-step predictive control method of the Small Modular Reactor Zhao, Mengwei

174 C p.
artikel
7 An optimization method of multi-objective evacuation path for off-site emergency under severe nuclear accidents Tang, Zhihong

174 C p.
artikel
8 Behaviors of type-I instabilities in natural circulation with a heating channel under ocean conditions Gong, Hou-jun

174 C p.
artikel
9 CFD simulation of instantaneous shape oscillation with rising velocity fluctuation for single bubble rising in water Mei, Zhongkai

174 C p.
artikel
10 Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors Massone, Mattia

174 C p.
artikel
11 Core design optimization of small modular dual fluid reactor based on NSGA-III in the aspect of reactor physics Chen, Runkai

174 C p.
artikel
12 Development and application of the improved multicell method for the PWR fuel assemblies adjacent to reflector Wan, Chenghui

174 C p.
artikel
13 Development and verification of a GPU-based MOC transient solver Zou, Hang

174 C p.
artikel
14 Development of a GPU-based three-dimensional neutron transport code Zhang, Ao

174 C p.
artikel
15 Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly Liu, Maolong

174 C p.
artikel
16 Development of a seven-region lumped parameter nonlinear dynamic model for U-tube recirculation nuclear steam generator Zhong, Xianping

174 C p.
artikel
17 Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD Liu, Maolong

174 C p.
artikel
18 Doppler broadening using discrete cosine transform and kernel reconstruction for spatially variable media Liu, Changyuan

174 C p.
artikel
19 Editorial Board
174 C p.
artikel
20 Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063] Brovchenko, M.

174 C p.
artikel
21 Experimental investigation of pool boiling heat transfer and bubble dynamics for the downward facing heating Tseng, Y.L.

174 C p.
artikel
22 Experimental investigation of solid particle spreading driven by gas injection into a pool of water Thakre, Sachin

174 C p.
artikel
23 Experimental investigation on sloshing motion in a liquid pool with binarily mixed-density solid particles Li, Shuo

174 C p.
artikel
24 Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly Liu, Maolong

174 C p.
artikel
25 Generalization of the tibere B1 leakage model to the method of characteristics Musongela, M.

174 C p.
artikel
26 Generation of localized reactor point kinetics parameters using coupled neutronic and thermal fluid models for pebble-bed reactor transient analysis Stewart, Ryan

174 C p.
artikel
27 Mitigating the numerical xenon instability in deterministic reactor burnup calculations Müller, Erwin

174 C p.
artikel
28 Natural convection compound heat transfer enhancement by discrete rings and the chimney effect in a vertical cylinder Njoroge, John

174 C p.
artikel
29 Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR) Dong, Zhengyang

174 C p.
artikel
30 Numerical study on satellite droplet formation in laminar jet breakup for a liquid droplet radiator Zhu, Maoguo

174 C p.
artikel
31 OpenFOAM CFD simulation of critical heat flux in vertical pipe under typically PWR conditions Dione, Fulgence

174 C p.
artikel
32 Optimization of the DC magnetohydrodynamic pump for the Dual Fluid Reactor Nowak, Mateusz

174 C p.
artikel
33 Polynomial interpolation cross-section parameterization method with the RMC Monte Carlo code Feng, Zhiyuan

174 C p.
artikel
34 Reactor space-dependent transfer function at low frequency approximated by neutron diffusion theory perturbation Anghel, V.N.P.

174 C p.
artikel
35 Research on coherent structure in 4-rod bundle lattice based on CFD Ma, Songyang

174 C p.
artikel
36 Research on static characteristics of capacitance rod position measurement sensor with protection electrodes Li, Yanlin

174 C p.
artikel
37 Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature Dougdag, Mourad

174 C p.
artikel
38 Safety archetypes identification and behavior simulation for nuclear power plant operation human reliability improvement Wu, Guanyin

174 C p.
artikel
39 Separator performance modeling and analysis using artificial neural network and response surface method Ouyang, Shuo

174 C p.
artikel
40 Study of transient events during the full-system chemical decontamination operation of the Kori-1 nuclear power plant Park, Jea-Ho

174 C p.
artikel
41 The effect of β on the consequence characteristics of a postulated criticality accident using 1/fβ spectrum in randomized model of material distribution Simanullang, Irwan Liapto

174 C p.
artikel
42 Uncertainty analyses of neutron noise simulations in a Zero-Power reactor Yum, S.

174 C p.
artikel
                             42 gevonden resultaten
 
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