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 |