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
 
                             31 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 ALFRED reactor and hybrid systems: A test case Chebac, Riccardo

191 C p.
artikel
2 BISON validation to in situ cladding burst test and high-burnup LOCA experiments Capps, N.

191 C p.
artikel
3 Depressurization strategy of automatic depressurization system for advanced pressurized water reactor Xing, Ji

191 C p.
artikel
4 Development of multiphase subchannel code with new numerical method in COSINE code package Chen, Lin

191 C p.
artikel
5 Eco-friendly transparent glass prepared from rice straw ash for neutron and charged particle radiation shielding Abdelgawad, K.R.M.

191 C p.
artikel
6 Editorial Board
191 C p.
artikel
7 Experimental analysis and two-region mixing coefficients development for a wire-wrapped tight lattice bundle Li, Junlong

191 C p.
artikel
8 Experimental research progress of grid to rod fretting in pressurized water reactors Jiao, Yong-jun

191 C p.
artikel
9 Experimental study on the influence of inclination on operating characteristics of secondary side passive residual heat removal system Sun, Ao

191 C p.
artikel
10 Full calculation of the long-time-interval limit of noise in reactors Gabrieli, G.

191 C p.
artikel
11 Heat transfer system design of sodium test facility STELLA-2 Lee, Jewhan

191 C p.
artikel
12 Integrated unavailability analysis including test degradation and efficiency, components ageing and common cause failures de Jesús Rivero Oliva, José

191 C p.
artikel
13 Measurement of dosimetrical cross sections with 14.05 MeV neutrons from compact neutron generator Kostal, Michal

191 C p.
artikel
14 Modal analysis of lead-bismuth eutectic flow in a single wire-wrapped rod channel Zhao, Xielin

191 C p.
artikel
15 Multi-physical fuel performance modeling of U-50Zr helical cruciform fuel based on fluid-thermal-structure coupling methodology Cai, Mengke

191 C p.
artikel
16 Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies Greenquist, Ian

191 C p.
artikel
17 Preliminary conceptual design of an electronuclear system for space applications Bertrand, F.

191 C p.
artikel
18 Rationalization and evaluation of a Phenomenon-driven improved bundle CHF model under PWRs condition with different axial power distributions Liu, Yang

191 C p.
artikel
19 Reduced-order with least square-finite difference method for neutron transport equation Chi, Honghang

191 C p.
artikel
20 Research on energy loss characteristics during transient process of reactor coolant pump shaft stuck accident Qu, Zehui

191 C p.
artikel
21 Research on optimization of momentum source model to supercritical carbon dioxide flow in wire wrapped rods bundle Liu, Sichao

191 C p.
artikel
22 Research on stability and control strategies for a spring-loaded valve with bypass outlet Jian, Jie

191 C p.
artikel
23 Research on the source-detector variance reduction method based on the AIS adjoint Monte Carlo method Hao, Yisheng

191 C p.
artikel
24 Results and lessons learned from the Generation IV SCWR-FQT comprehensive Monte Carlo computational benchmark Babcsány, Boglárka

191 C p.
artikel
25 SMR, 3D source term simulation for exact shielding design based on genetic algorithm Bagheri, S.

191 C p.
artikel
26 Study of the thermal expansion effects of a space nuclear reactor with an integrated honeycomb core design using OpenMC and ANSYS Chen, Chao

191 C p.
artikel
27 The impact of nuclear data uncertainty on identifying plutonium diversion in liquid-fueled Molten Salt Reactors Vidal Soares, Andre

191 C p.
artikel
28 The reverse flow among parallel U-tubes in steam generator under natural circulation condition: A review Jianli, Hao

191 C p.
artikel
29 Towards optimized designs for control rod absorbers with a high-fidelity simulation method implemented in the RMC code Luo, Hao

191 C p.
artikel
30 Uncertainty quantification for severe-accident reactor modelling: Set-up and first results of the Horizon-2020 project MUSA Brumm, S.

191 C p.
artikel
31 Whole core analysis of the single-fluid double-zone heavy water-moderated molten salt reactor (SD-HWMSR) Ashraf, O.

191 C p.
artikel
                             31 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland