| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A method for hazard analysis of a floating nuclear power plant subjected to ship collision
|
Xiao, Jinxiong
|
|
|
190 |
C |
p.
|
artikel
|
| 2 |
An Adaptive Time-Stepping Control Algorithm for Molten Salt Reactor Transient Analyses
|
Jaradat, Mustafa K.
|
|
|
190 |
C |
p.
|
artikel
|
| 3 |
A new point kinetics model for ADS-type reactor using the importance function associated to the fission rate as weight function
|
Salas, L.L.
|
|
|
190 |
C |
p.
|
artikel
|
| 4 |
An innovative method for building the model of oxidation resistance of Cr coatings
|
Zeng, Song
|
|
|
190 |
C |
p.
|
artikel
|
| 5 |
Autonomous control model for emergency operation of small modular reactor
|
Saeed, Hanan A
|
|
|
190 |
C |
p.
|
artikel
|
| 6 |
CFD analysis of porous flow blockage in a gas-lift enhanced LBE-cooled fuel assembly
|
Xia, Fan
|
|
|
190 |
C |
p.
|
artikel
|
| 7 |
Control strategy study for a heat pipe cooled nuclear reactor
|
Zhang, Xianshan
|
|
|
190 |
C |
p.
|
artikel
|
| 8 |
Corrigendum to “Proliferation resistance of light water reactor versus pebble bed reactor” [Ann. Nucl. Energy 188 (2023) 1–12]
|
Mulyana, Dany
|
|
|
190 |
C |
p.
|
artikel
|
| 9 |
Development of a hybrid parallelism Monte Carlo transport middleware on mesh geometry
|
Wang, Xin
|
|
|
190 |
C |
p.
|
artikel
|
| 10 |
Development of a surrogate model for quenching estimation of ex-vessel debris beds and its coupling with MELCOR
|
Wang, Wanhong
|
|
|
190 |
C |
p.
|
artikel
|
| 11 |
Development of OpenMC/Trivac two-step scheme for fast reactor core neutronics analysis
|
Guo, Hui
|
|
|
190 |
C |
p.
|
artikel
|
| 12 |
Discrete element simulation of Pebble Bed Reactors on graphics processing units
|
Reger, David
|
|
|
190 |
C |
p.
|
artikel
|
| 13 |
Double heterogeneity effect analysis for plate fuel with dispersed particles
|
Yuan, Anmin
|
|
|
190 |
C |
p.
|
artikel
|
| 14 |
Droplet group combustion model improvement for sodium spray fire pre-combustion analysis
|
Zou, Zhenyu
|
|
|
190 |
C |
p.
|
artikel
|
| 15 |
Editorial Board
|
|
|
|
190 |
C |
p.
|
artikel
|
| 16 |
Effect of changing the outer fuel element diameter on thermophysical parameters of KLT-40S reactor unit
|
Beliavskii, S.
|
|
|
190 |
C |
p.
|
artikel
|
| 17 |
ERMSAR-2022 conference “Severe accident research: Eleven years after the Fukushima accident”
|
Herranz, Luis E.
|
|
|
190 |
C |
p.
|
artikel
|
| 18 |
Experiments on axial-flow-induced vibration of a free-clamped/clamped-free rod for light-water nuclear reactor applications
|
Cioncolini, Andrea
|
|
|
190 |
C |
p.
|
artikel
|
| 19 |
Fuel cycle depletion validation and code-to-code verification studies for High Flux Isotope Reactor highly and low-enriched uranium fuel designs
|
Chandler, David
|
|
|
190 |
C |
p.
|
artikel
|
| 20 |
Hybrid Data Assimilation methods, Part II: Application to the DYNASTY experimental facility
|
Riva, Stefano
|
|
|
190 |
C |
p.
|
artikel
|
| 21 |
Hybrid data assimilation methods, Part I: Numerical comparison between GEIM and PBDW
|
Riva, Stefano
|
|
|
190 |
C |
p.
|
artikel
|
| 22 |
Identification of the effective thermal conductivity law in a nuclear fuel rod for the evaluation of neutronic feedbacks
|
Dall’Osso, Aldo
|
|
|
190 |
C |
p.
|
artikel
|
| 23 |
Mechanical defects in the “p-TRISO”-particle covering layers obtained through the ion implantation process
|
Krajewska, Zuzanna M.
|
|
|
190 |
C |
p.
|
artikel
|
| 24 |
Performance of potentiometric oxygen sensors with LSCF electrode in lead–bismuth eutectic loop
|
Liang, Ruixian
|
|
|
190 |
C |
p.
|
artikel
|
| 25 |
Preliminary neutronics and thermal analysis of a heat pipe cooled traveling wave reactor
|
Ma, Kunfeng
|
|
|
190 |
C |
p.
|
artikel
|
| 26 |
Probabilistic monitoring of nuclear plants using R-vine copula
|
Amin, Md Tanjin
|
|
|
190 |
C |
p.
|
artikel
|
| 27 |
Research on effects of rolling motion on a pressurizer surge line based on the fluid-solid-thermal coupling method
|
Yu, Hang
|
|
|
190 |
C |
p.
|
artikel
|
| 28 |
Study of the radioactivity inventory deposited in the reactor coolant system during the decommissioning of Kori Unit 1
|
Park, Jea-Ho
|
|
|
190 |
C |
p.
|
artikel
|
| 29 |
Study on the lower head failure in severe accident Part I: Model development and validation
|
Gao, Pengcheng
|
|
|
190 |
C |
p.
|
artikel
|
| 30 |
Thermal hydraulic design and mass optimization of a 100-kWe S-CO2 cooled Mars-surface fission reactor system
|
Xue, Qi
|
|
|
190 |
C |
p.
|
artikel
|
| 31 |
Time-dependent neutronics model of nodal neutronics program Ants
|
Rintala, Antti
|
|
|
190 |
C |
p.
|
artikel
|
| 32 |
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F
|
Zullo, G.
|
|
|
190 |
C |
p.
|
artikel
|
| 33 |
Transient analyses for China initiative Accelerator Driven System using the extended BELLA code
|
Wang, Guan
|
|
|
190 |
C |
p.
|
artikel
|
| 34 |
Uncertainty analysis of the control rod drop based on the adaptive collocation stochastic perturbation method
|
Wu, Feng
|
|
|
190 |
C |
p.
|
artikel
|
| 35 |
Uncertainty quantification and target accuracy assessment of nuclear data to effective neutron multiplication factor of heat pipe cooled reactor
|
Qin, Kaiwen
|
|
|
190 |
C |
p.
|
artikel
|
| 36 |
Validating Kraken for VVER-1000 fuel cycle simulations using the X2 benchmark
|
Valtavirta, Ville
|
|
|
190 |
C |
p.
|
artikel
|
| 37 |
Validation of the Ants-TRACE code system with VVER-1000 coolant transient benchmarks
|
Lauranto, Unna
|
|
|
190 |
C |
p.
|
artikel
|
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