| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A framework to implement human reliability analysis during early design stages of advanced reactors
|
Hamza, Mostafa
|
|
|
146 |
C |
p.
|
artikel
|
| 2 |
Analysis of historic fires to determine most frequent challenging events
|
Salvi, Urvin
|
|
|
146 |
C |
p.
|
artikel
|
| 3 |
Analysis of 3-layer corium pool models in CISER2.0 code
|
Liu, Lili
|
|
|
146 |
C |
p.
|
artikel
|
| 4 |
A preliminary analysis on optimization of core flow distribution
|
Xu, Haipeng
|
|
|
146 |
C |
p.
|
artikel
|
| 5 |
Assessment of mechanical and radiation shielding capacity for a ternary CdO–BaO–B2O3 glass system: A comprehensive experimental, Monte Carlo simulation, and theoretical studies
|
Mahmoud, K.A.
|
|
|
146 |
C |
p.
|
artikel
|
| 6 |
A state-aware adaptive pathfinder for dynamic minimum dose path planning during an emergency in a complex radioactive environment
|
Miyombo, Miyombo Ernest
|
|
|
146 |
C |
p.
|
artikel
|
| 7 |
Development of ANN structural optimization framework for data-driven prediction of local two-phase flow parameters
|
Nguyen, Ngoc Dat
|
|
|
146 |
C |
p.
|
artikel
|
| 8 |
Editorial Board
|
|
|
|
146 |
C |
p.
|
artikel
|
| 9 |
Experimental investigation on thermal hydraulic interaction of RCS (reactor coolant system) and containment for intermediate break loss-of-coolant accident (IBLOCA) scenario in ATLAS-CUBE test facility
|
Bae, Byoung-Uhn
|
|
|
146 |
C |
p.
|
artikel
|
| 10 |
Explicit modeling of pebble temperature in the porous-media model for pebble-bed reactors
|
Zou, Ling
|
|
|
146 |
C |
p.
|
artikel
|
| 11 |
Fission source stationarity diagnostics using the Fourier fundamental mode coefficient
|
Omar, M.R.
|
|
|
146 |
C |
p.
|
artikel
|
| 12 |
GeN-ROM—An OpenFOAM®-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors
|
German, Péter
|
|
|
146 |
C |
p.
|
artikel
|
| 13 |
Heat transfer experiment with the prototypical Ra number of heavy metallic layer in IVR strategy
|
Li, Zongyang
|
|
|
146 |
C |
p.
|
artikel
|
| 14 |
High volume packing fraction TRISO-based fuel in light water reactors
|
Brown, Nicholas R.
|
|
|
146 |
C |
p.
|
artikel
|
| 15 |
Improved TDV algorithm for three-dimensional space path planning in a complex radioactive environment with obstacles
|
Miyombo, Miyombo Ernest
|
|
|
146 |
C |
p.
|
artikel
|
| 16 |
Negative temperature coefficients of reactivity for metallic fuel Dual Fluid Reactor
|
Sierchuła, Jakub
|
|
|
146 |
C |
p.
|
artikel
|
| 17 |
Numerical simulation of gas holdup in nocoalescence media of industrial-scale bubble column
|
Wen, Jiming
|
|
|
146 |
C |
p.
|
artikel
|
| 18 |
Performance evaluation of composite-barrier system against migration of tin from radioactive wastes: Approaches in terms of risk assessments
|
Durmus, R.K. Ileri
|
|
|
146 |
C |
p.
|
artikel
|
| 19 |
Physically adversarial thermal hydraulics evaluation of deep learning models for pressurized water reactors
|
Shriver, Forrest
|
|
|
146 |
C |
p.
|
artikel
|
| 20 |
Pilot numerical study of new design of passive residual heat removal heat exchanger tubes
|
Wu, Hsingtzu
|
|
|
146 |
C |
p.
|
artikel
|
| 21 |
Predictions of component Remaining Useful Lifetime Using Bayesian Neural Network
|
Rivas, Andy
|
|
|
146 |
C |
p.
|
artikel
|
| 22 |
Radioactive waste management in the UAE: Proposal for an inventory management system
|
Al Nuaimi, Abdulla Hashim
|
|
|
146 |
C |
p.
|
artikel
|
| 23 |
Scaling deep learning for whole-core reactor simulation
|
Shriver, Forrest
|
|
|
146 |
C |
p.
|
artikel
|
| 24 |
Selection of the best 3-section squared-off cascade to enrichment of the 126Xe and 131Xe using particle swarm optimization algorithm
|
Mirmohammadi, S.L.
|
|
|
146 |
C |
p.
|
artikel
|
| 25 |
Study of comprehensive shielding behaviors of chambersite deposit for neutron and gamma ray
|
Dong, Mengge
|
|
|
146 |
C |
p.
|
artikel
|
| 26 |
Study of natural uranium utilization in a heavy water moderated molten salt reactor
|
Wu, Jianhui
|
|
|
146 |
C |
p.
|
artikel
|
| 27 |
The development of high temperature heat-pipe transient model for system analysis of heat pipe cooled microreactor
|
Huaqi, Li
|
|
|
146 |
C |
p.
|
artikel
|
| 28 |
Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators
|
Zhang, Yin
|
|
|
146 |
C |
p.
|
artikel
|
| 29 |
Uncertainty analysis of HPR-1000 LOCA with probabilistic and deterministic methods
|
Chen, Wei
|
|
|
146 |
C |
p.
|
artikel
|
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