| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A numerical investigation of an indoor dry storage facility on heat transfer
|
Lin, Chia-Wei
|
|
|
196 |
C |
p.
|
artikel
|
| 2 |
Bicyclus: A statistical fuel cycle simulation framework for nuclear verification
|
Schalz, Max
|
|
|
196 |
C |
p.
|
artikel
|
| 3 |
CFD analysis of curvature and inclination effect on steam condensation in the presence of air
|
Zhou, Shuhang
|
|
|
196 |
C |
p.
|
artikel
|
| 4 |
Dependency analysis method for human failure events in level 2 probabilistic safety assessment of nuclear power plants
|
Chen, Shuai
|
|
|
196 |
C |
p.
|
artikel
|
| 5 |
Development and verification of a one-dimensional collision probability based neutron transport code to model axially heterogeneous cylindrical vessels containing aqueous and organic plutonium nitrate
|
Daniels, J.R.
|
|
|
196 |
C |
p.
|
artikel
|
| 6 |
Development of a site release category model and its application
|
Cho, Mina
|
|
|
196 |
C |
p.
|
artikel
|
| 7 |
Distributed collaboration: Cognitive difference and collaborative decision for multi-robot radioactive source search
|
Luo, Minghua
|
|
|
196 |
C |
p.
|
artikel
|
| 8 |
Editorial Board
|
|
|
|
196 |
C |
p.
|
artikel
|
| 9 |
Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident
|
Greenquist, Ian
|
|
|
196 |
C |
p.
|
artikel
|
| 10 |
Emission of the backscattered electron in the energy range of 20 to100 keV
|
Xie, Aigen
|
|
|
196 |
C |
p.
|
artikel
|
| 11 |
Enhancing prediction accuracy for LOCA break sizes in nuclear power plants: A hybrid deep learning method with data augmentation and hyperparameter optimization
|
Zhou, Gui
|
|
|
196 |
C |
p.
|
artikel
|
| 12 |
Enhancing the density and crush load of Li2TiO3 tritium breeding ceramic pebbles by adding LiNO3-Li2CO3
|
Gong, Yichao
|
|
|
196 |
C |
p.
|
artikel
|
| 13 |
Expert knowledge modelling software design based on Signed Directed Graph with the application for PWR fault diagnosis
|
Ma, Zhanguo
|
|
|
196 |
C |
p.
|
artikel
|
| 14 |
Extending TRANSURANUS burnup model for AGR-like FHR fuel design
|
de Lara, A.
|
|
|
196 |
C |
p.
|
artikel
|
| 15 |
Fast uncertainty quantification of spent nuclear fuel with neural networks
|
Albà, Arnau
|
|
|
196 |
C |
p.
|
artikel
|
| 16 |
Fault diagnosis of spent fuel shearing machines based on improved residual network
|
Pingping, Wang
|
|
|
196 |
C |
p.
|
artikel
|
| 17 |
FEMFFUSION and its verification using the C5G7 benchmark
|
Fontenla, Y.
|
|
|
196 |
C |
p.
|
artikel
|
| 18 |
Improvement of LLFPs transmutation efficiency by moderator loading in lead-based fast neutron reactor
|
Sun, Xiang-yang
|
|
|
196 |
C |
p.
|
artikel
|
| 19 |
Intelligent nuclear decommissioning solution: Code for site characterization and management of overall surveys
|
Byun, Hyungi
|
|
|
196 |
C |
p.
|
artikel
|
| 20 |
Investigation of aerosol transportation phenomena in pool scrubbing by combining bubble plume measurements and single-bubble mass transfer analysis
|
Fujiwara, Kota
|
|
|
196 |
C |
p.
|
artikel
|
| 21 |
Iodine source term assessment under DBA SGTR accident scenario
|
Bousbia Salah, A.
|
|
|
196 |
C |
p.
|
artikel
|
| 22 |
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
|
Mascari, F.
|
|
|
196 |
C |
p.
|
artikel
|
| 23 |
Multi-physics coupled analyzes of research nuclear reactors based on steady-state and kinetics models
|
Zhang, Tengfei
|
|
|
196 |
C |
p.
|
artikel
|
| 24 |
Nuclear data sensitivity and uncertainty analysis using a set of benchmarks containing 233 U comparing ENDF/B-VII.1 and ENDF/B- VIII.0 libraries
|
Hadouachi, M.
|
|
|
196 |
C |
p.
|
artikel
|
| 25 |
Numerical simulation and optimization of In-Vessel primary heat exchangers of NHR200-II
|
Yiwa, Geng
|
|
|
196 |
C |
p.
|
artikel
|
| 26 |
Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions
|
Yuan, Lanfei
|
|
|
196 |
C |
p.
|
artikel
|
| 27 |
Optimization analysis of thermal–hydraulic features of the 2.5 MW LBE spallation target of CiADS
|
Deng, Weiping
|
|
|
196 |
C |
p.
|
artikel
|
| 28 |
Parallelization and optimization for a pin-by-pin whole core thermal–hydraulic analysis code
|
Luo, Xiao
|
|
|
196 |
C |
p.
|
artikel
|
| 29 |
Radiation damage analysis of the first generation VVER spent nuclear fuel casks
|
Lovecký, M.
|
|
|
196 |
C |
p.
|
artikel
|
| 30 |
Reflective reviews on Japanese high-level waste (HLW) vitrification – Exploring the obstacles encountered in active tests at Rokkasho
|
Sakai, Akira
|
|
|
196 |
C |
p.
|
artikel
|
| 31 |
Research on the influence of nonuniform inflow on steady-state hydraulic performance of reactor coolant pump
|
Lu, Jinqi
|
|
|
196 |
C |
p.
|
artikel
|
| 32 |
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems
|
Hartanto, Donny
|
|
|
196 |
C |
p.
|
artikel
|
| 33 |
SN-MscaleDNN: A coupling approach for rapid shielding-scheme evaluation of micro gas-cooled reactor in the large design-parameter space
|
Lei, Kaihui
|
|
|
196 |
C |
p.
|
artikel
|
| 34 |
Study on heat transfer characteristics of supercritical CO2/propane mixtures in vertical tube
|
Yin, Dandan
|
|
|
196 |
C |
p.
|
artikel
|
| 35 |
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility
|
Zhang, Rong
|
|
|
196 |
C |
p.
|
artikel
|
| 36 |
TARS: A parallel tetrahedral discontinuous finite element code for the solution of the discrete ordinates neutron transport equation
|
Zhang, Guangchun
|
|
|
196 |
C |
p.
|
artikel
|
| 37 |
Testing of fiber optic based sensors for advanced reactors in the Texas A&M University TRIGA reactor
|
Tyler Gates, J.
|
|
|
196 |
C |
p.
|
artikel
|
| 38 |
The influence of graphite moderator density on the neutronic performance and fuel economy of a Molten Salt Reactor
|
Dwijayanto, R. Andika Putra
|
|
|
196 |
C |
p.
|
artikel
|
| 39 |
The study on the main factors affecting the response analysis of nuclear fuel transport cask drop
|
Lan, Tianbao
|
|
|
196 |
C |
p.
|
artikel
|
| 40 |
The technology of suppression containment for the SMR in floating nuclear power plants against hydrogen risk
|
Chen, Jialei
|
|
|
196 |
C |
p.
|
artikel
|
Tijdschrift beschrijving