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
 
                             36 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Advancing nuclear science education through IRL Integration: A case experiment on criticality mass determination at the Kartini research reactor Zubair, Muhammad

204 C p.
artikel
2 Analysis of power transients in the CABRI experimental reactor with a multi-physics APOLLO3®/THEDI coupling Vaglio-Gaudard, C.

204 C p.
artikel
3 A new algorithm of critical control rod position search in MC code Li, Rui

204 C p.
artikel
4 A new method of fuel pebble temperature calculation based on neutronic and thermal coupling equivalent model Wang, Jincheng

204 C p.
artikel
5 A theoretical model of gas column breakup under a swirling flow field based on the jet theory Zhang, Jiarong

204 C p.
artikel
6 Automated group constant parameterization for low sample sizes using different Machine learning approaches Sebestény, Dániel

204 C p.
artikel
7 A variational autoencoder for minimally-supervised pulse shape discrimination Abdulaziz, Abdullah

204 C p.
artikel
8 Burnup study on the effective transmutation of minor actinides based on multi-enrichment fuel in the ADS subcritical reactor Meng, Haiyan

204 C p.
artikel
9 Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor Kelsingazina, Ruziya

204 C p.
artikel
10 Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067] Williams, M.M.R.

204 C p.
artikel
11 Development of a simplified one-dimensional CDA bubble model Zou, Zeren

204 C p.
artikel
12 3D numerical simulation on thermal hydraulic characteristics in integrated sodium pool of PHENIX reactor during dissymmetric test Zhao, Haiqi

204 C p.
artikel
13 Dynamic modelling of flexible dispatch in a novel nuclear-solar integrated energy system with thermal energy storage Rigby, Aidan

204 C p.
artikel
14 Editorial Board
204 C p.
artikel
15 Effects of internal pressure and heating rate on the burst behaviors of Cr-coated cladding during simulated LOCA testing Duan, Zhengang

204 C p.
artikel
16 Enhancing passive gamma emission tomography data with deep learning Sanchez-Belenguer, Carlos

204 C p.
artikel
17 Experimental investigation on steam condensation characteristics in horizontal heat transfer pipe of PRS for HPR1000 Sun, D.C.

204 C p.
artikel
18 Experimental study on convective heat transfer characteristics of fluoride salt outside the tube bundle in hairpin heat exchanger Chen, Y.S.

204 C p.
artikel
19 Experimental study on pressure fluctuation in header of nuclear power plant SEC system after long-term pump shutdown Chen, Yiming

204 C p.
artikel
20 Four-sensor droplet-capable conductivity probe in annular and wispy-annular flows Tsoukalas, Charie A.

204 C p.
artikel
21 Heat transfer characteristics analysis of heat pipe based on COMSOL Pan, Rui

204 C p.
artikel
22 Hydrogen uptake of zirconium alloys in defective fuel rods: Experiment and numerical model Szabó, P.

204 C p.
artikel
23 Improving conversion process of cross-section data into multipole parameters using rational Krylov approximation Agh, Abdolbaset

204 C p.
artikel
24 Microstructure evolution and mechanical properties of ODS FeCrAl alloys fabricated by spark plasma sintering Yan, Xu

204 C p.
artikel
25 Modeling of transient and steady state xenon behavior in the molten salt reactor experiment Chen, Jiaqi

204 C p.
artikel
26 Nuclear education programs with reactor laboratory experiments at zero-powered research reactor facilities in Japan Pyeon, Cheol Ho

204 C p.
artikel
27 Nuclear fuels for transient test reactors Woolstenhulme, Nicolas

204 C p.
artikel
28 Numerical Monte Carlo analysis of the void coefficient in Pavia TRIGA Mark II reactor Boccelli, Riccardo

204 C p.
artikel
29 Numerical study on the condensation characteristics of vapor with non-condensable gas on inclined walls inside containment Cai, J.Y.

204 C p.
artikel
30 On the use of neutron flux gradient with ANNs for the detection of diverted spent nuclear fuel Al-dbissi, Moad

204 C p.
artikel
31 Precise modelling and operation characteristics analysis of the small helium-xenon gas cooled reactor power system with the air heat sink Liao, Haoyang

204 C p.
artikel
32 Research and educational applications of the Aerojet General Nucleonics 201-M at the University of New Mexico Davis, Rowdy

204 C p.
artikel
33 Research on prediction of non-uniform heated rod bundle CHF based on subchannel analysis code coupling modified mechanistic model Zhu, Gan

204 C p.
artikel
34 SACOS-PLATE: A new thermal-hydraulic subchannel analysis code for plate type fuel assemblies Sun, Ruiyu

204 C p.
artikel
35 Study on safety gap between fuel channels in NHR200-II Zheng, Junzheng

204 C p.
artikel
36 U-50Zr helical cruciform fuel performance analysis based on MOOSE framework Hou, Yandong

204 C p.
artikel
                             36 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland