| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A control rod worth prediction using Adaptive Neuro-Fuzzy Inference System for Pre-Calibration Method at TRIGA PUSPATI Reactor
|
Zhi Hui, Teh
|
|
|
200 |
C |
p.
|
artikel
|
| 2 |
A gasket design suitable for helium circuits of generation IV Gas-Cooled reactors
|
Staf, Marek
|
|
|
200 |
C |
p.
|
artikel
|
| 3 |
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code
|
Wang, Tao
|
|
|
200 |
C |
p.
|
artikel
|
| 4 |
Autonomous control for Heat-Pipe microreactor using Data-Driven model predictive control
|
Lin, Linyu
|
|
|
200 |
C |
p.
|
artikel
|
| 5 |
Coolant radiolysis near the saturation temperature in a VVER core
|
Ivanov, A.S.
|
|
|
200 |
C |
p.
|
artikel
|
| 6 |
Development of multi-scale thermal hydraulic analysis code, CUPID/SPACE based on implicit code coupling scheme
|
Choi, Chiwoong
|
|
|
200 |
C |
p.
|
artikel
|
| 7 |
Editorial Board
|
|
|
|
200 |
C |
p.
|
artikel
|
| 8 |
Effects of boric acid on volatile tellurium in severe accident conditions
|
Börjesson Sandén, Fredrik
|
|
|
200 |
C |
p.
|
artikel
|
| 9 |
Evaluation of hydrogen generation from feeder pipes of CANDU reactor
|
Ho Bae, Jun
|
|
|
200 |
C |
p.
|
artikel
|
| 10 |
Evaluation of sampling methods for nuclear data uncertainty quantification
|
Zou, Xiaoyang
|
|
|
200 |
C |
p.
|
artikel
|
| 11 |
Experimental investigation of high-temperature water flow boiling characteristics in plate-fin heat exchanger for nuclear cooling
|
Lu, Shuaiting
|
|
|
200 |
C |
p.
|
artikel
|
| 12 |
Experimental investigations on the two-phase water entrainment phenomenon at inclined branch T-junctions and numerical simulations based on neptune_cfd
|
Ma, Xinran
|
|
|
200 |
C |
p.
|
artikel
|
| 13 |
Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISON
|
Dunbar, Cole
|
|
|
200 |
C |
p.
|
artikel
|
| 14 |
Implementation of the steady state simplified P3 (SP3) transport solver in the finite element neutronic code FENNECS, Part 1: Theory
|
lo Muzio, Silvia
|
|
|
200 |
C |
p.
|
artikel
|
| 15 |
Implementation of the steady state Simplified P3 (SP3) transport solver in the finite element neutronic code FENNECS, Part 2: Verification
|
lo Muzio, Silvia
|
|
|
200 |
C |
p.
|
artikel
|
| 16 |
Improved radiation shielding properties of epoxy resin composites using Sb2O3 and Al2O3 nanoparticles additives
|
Darwesh, Reem
|
|
|
200 |
C |
p.
|
artikel
|
| 17 |
Inventory and solubility of fission products in molten lead to quantify source term in lead-cooled fast reactors
|
Fitzhugh, Richard L.
|
|
|
200 |
C |
p.
|
artikel
|
| 18 |
Machine learning at the edge to improve in-field safeguards inspections
|
Shoman, Nathan
|
|
|
200 |
C |
p.
|
artikel
|
| 19 |
Manufacturing high-uranium-loaded dispersion fuel plates in Brazil
|
Durazzo, Michelangelo
|
|
|
200 |
C |
p.
|
artikel
|
| 20 |
Mapping radioactive environments by use of sparse Gaussian processes regression
|
Kipkosgei, C. Amos
|
|
|
200 |
C |
p.
|
artikel
|
| 21 |
Multilayer radiation shields for nuclear and radiological centers using free-lead materials and nanoparticles
|
Almuqrin, Aljawhara H.
|
|
|
200 |
C |
p.
|
artikel
|
| 22 |
Neutron transport methods for multiphysics heterogeneous reactor core simulation in Griffin
|
Prince, Zachary M.
|
|
|
200 |
C |
p.
|
artikel
|
| 23 |
Numerical investigation on flow and heat transfer characteristics of a PCHE with liquid lead–bismuth eutectic and sCO2 as working fluids
|
Liu, Hong
|
|
|
200 |
C |
p.
|
artikel
|
| 24 |
Prediction of critical heat flux in rod bowing geometries by coupled subchannel analysis and mechanistic model
|
Guo, Junliang
|
|
|
200 |
C |
p.
|
artikel
|
| 25 |
Preliminary design and assessment of a novel passive residual heat removal system for the pool-vessel reactor system
|
Zhang, Wenwen
|
|
|
200 |
C |
p.
|
artikel
|
| 26 |
Proposal of weighting options for influencing factors and method of giving preference to alternatives for selecting the preliminary decommissioning strategy of Kori-1
|
Jung, Hye-Jin
|
|
|
200 |
C |
p.
|
artikel
|
| 27 |
Study of the DVI-LOCA in the AP1000-like reactor with MELCOR code
|
Włostowski, Mateusz
|
|
|
200 |
C |
p.
|
artikel
|
| 28 |
Study on the safety characteristics of fluoride-salt-cooled high-temperature advanced reactor
|
Lv, Xindi
|
|
|
200 |
C |
p.
|
artikel
|
| 29 |
Thermal consolidation modeling of unsaturated soil with semi-permeable boundary: Semi-analytical and numerical investigation
|
Meng, Hongping
|
|
|
200 |
C |
p.
|
artikel
|
| 30 |
Thermal-hydraulic characteristics of helical coiled once-through steam generators in inclining condition of ocean
|
Hou, Yandong
|
|
|
200 |
C |
p.
|
artikel
|
| 31 |
Transient multi-physics coupling analysis of the Xi'an Pulsed Reactor under pulsed condition
|
Jiang, Duoyu
|
|
|
200 |
C |
p.
|
artikel
|
| 32 |
Transient multi-scale coupling analysis and its time sensitivity of Xi’an pulsed reactor
|
Zhao, Wei
|
|
|
200 |
C |
p.
|
artikel
|
| 33 |
Utilizing artificial neural networks to convert gamma-ray spectra from NaI(Tl) detectors to HPGe detector gamma-ray spectra
|
Saeidi, Zohreh
|
|
|
200 |
C |
p.
|
artikel
|
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