| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accident parameter prediction method for lead-bismuth cooled reactor based on a multivariate LSTM network coupled with an optimization algorithm
|
Chen, Zhifei
|
|
|
193 |
C |
p.
|
artikel
|
| 2 |
Adaptive time multiscale algorithms for fluid–structure interaction with impacts - Application to a row of PWR fuel assemblies under seismic loading
|
Faucher, V.
|
|
|
193 |
C |
p.
|
artikel
|
| 3 |
A finite element approach for nonlinear, transient heat conduction problems with convection, radiation or contact boundary conditions
|
Lu, Qiyue
|
|
|
193 |
C |
p.
|
artikel
|
| 4 |
A general method for delay compensation of self-powered neutron detectors in reactors
|
Liu, Shiyu
|
|
|
193 |
C |
p.
|
artikel
|
| 5 |
An assessment of scaling methods for ECC behavior in downcomer of UPTF with RELAP5 code
|
Wan, Jie
|
|
|
193 |
C |
p.
|
artikel
|
| 6 |
A new meteorological pressure index to support a sustainable nuclear energy programme
|
Giardina, M.
|
|
|
193 |
C |
p.
|
artikel
|
| 7 |
A systematic approach in the development of generic biosphere conceptual models for groundwater release into the Korean biosphere system from a spent nuclear fuel deep geological repository
|
Kim, Dongki
|
|
|
193 |
C |
p.
|
artikel
|
| 8 |
Burnup-control drum coupling characteristics investigation of lead–bismuth eutectic-cooled solid reactor
|
Yang, Qing
|
|
|
193 |
C |
p.
|
artikel
|
| 9 |
Constructing a probability digital twin for reactor core with Bayesian network and reduced-order model
|
Li, Wenhuai
|
|
|
193 |
C |
p.
|
artikel
|
| 10 |
Corrigendum to “Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor” [Ann. Nucl. Energy 96 (2016) 446–454]
|
Vela-García, M.
|
|
|
193 |
C |
p.
|
artikel
|
| 11 |
Depletion chain simplification using pseudo-nuclides
|
Calvin, Olin
|
|
|
193 |
C |
p.
|
artikel
|
| 12 |
Design, Modeling, and Analysis of a Compact-External Electromagnetic Pumping System for Pool-Type Liquid Metal-Cooled Fast Reactors
|
Shutayfi, Mohammed
|
|
|
193 |
C |
p.
|
artikel
|
| 13 |
Development and validation of a one-dimensional solidification model — Part I: Analytical model
|
Zeng, Chen
|
|
|
193 |
C |
p.
|
artikel
|
| 14 |
Development and validation of a one-dimensional solidification model — Part II: Model validation for molten lead-bismuth
|
Zeng, Chen
|
|
|
193 |
C |
p.
|
artikel
|
| 15 |
Editorial Board
|
|
|
|
193 |
C |
p.
|
artikel
|
| 16 |
Effects of grain boundaries and temperature on spinodal decomposition in a binary Fe-Cr alloy: A phase-field simulation
|
Yang, Zhaoxi
|
|
|
193 |
C |
p.
|
artikel
|
| 17 |
Error analyses and evaluation for solving burnup equations with MMPA method
|
Zhang, Binhang
|
|
|
193 |
C |
p.
|
artikel
|
| 18 |
Experimental study of flow field and transition characteristics in rod bundle channel
|
Qi, Peiyao
|
|
|
193 |
C |
p.
|
artikel
|
| 19 |
Extension of droplet/aerosol heat transfer model coupling Lagrangian approach in containment atmosphere under severe accident
|
Wang, Fangnian
|
|
|
193 |
C |
p.
|
artikel
|
| 20 |
Feasibility of neutron coincidence counting for spent TRISO fuel
|
Fang, Ming
|
|
|
193 |
C |
p.
|
artikel
|
| 21 |
High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient
|
Ridley, Mackenzie
|
|
|
193 |
C |
p.
|
artikel
|
| 22 |
Identification of diversions in spent PWR fuel assemblies by PDET signatures using Artificial Neural Networks (ANNs)
|
Al-dbissi, Moad
|
|
|
193 |
C |
p.
|
artikel
|
| 23 |
Improvement of a deterministic fuel management code using artificial neural network for liquid-fueled molten salt reactor
|
Yu, Kaicheng
|
|
|
193 |
C |
p.
|
artikel
|
| 24 |
Molecular dynamics study of fission product behaviour in molten T h F 4 - L i F salt
|
Maxwell, Christopher I.
|
|
|
193 |
C |
p.
|
artikel
|
| 25 |
Multi-physics core analysis and verification of NuScale reactor with coupling PARCS/RELAP
|
Kakaei, Pouria
|
|
|
193 |
C |
p.
|
artikel
|
| 26 |
Neutronic analysis of ABR-1000 sodium cooled fast reactor with radially and axially heterogeneous core configurations
|
Niloy, Md. Hasebul Hasan
|
|
|
193 |
C |
p.
|
artikel
|
| 27 |
Noise resistant steam generator water level reconstruction for nuclear power plant based on deep residual shrinkage network
|
Yue, Peng
|
|
|
193 |
C |
p.
|
artikel
|
| 28 |
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions
|
Liu, Jian
|
|
|
193 |
C |
p.
|
artikel
|
| 29 |
Parallel implementation of Red–Black ordering preconditioners for accelerating GMRES solutions in neutron transport code PANDAS-MOC
|
Tao, Shunjiang
|
|
|
193 |
C |
p.
|
artikel
|
| 30 |
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method
|
Wang, Jiaqiong
|
|
|
193 |
C |
p.
|
artikel
|
| 31 |
Research of dynamic rod worth measurement technique based on the pin-by-pin response function
|
Bai, Jiahe
|
|
|
193 |
C |
p.
|
artikel
|
| 32 |
Research on autonomous decision-making technology for once-through steam generator
|
Yu, Ren
|
|
|
193 |
C |
p.
|
artikel
|
| 33 |
Research on safety characteristics of heat pipe reactor with semiconductor thermoelectric conversion system
|
Wu, Pan
|
|
|
193 |
C |
p.
|
artikel
|
| 34 |
Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains
|
Hózer, Z.
|
|
|
193 |
C |
p.
|
artikel
|
| 35 |
Steady-state performance analysis of loop heat pipe radiator in space reactor
|
Xia, Genglei
|
|
|
193 |
C |
p.
|
artikel
|
| 36 |
Strengths and weaknesses of the modal expansion method for perturbations calculations in nuclear reactor physics
|
Sauzedde, Thibault
|
|
|
193 |
C |
p.
|
artikel
|
| 37 |
Study on the characteristics of axial fluid excitation on fuel rods with spacer grids
|
Li, Wei
|
|
|
193 |
C |
p.
|
artikel
|
| 38 |
The neutron number probability distribution in coupled lumped assemblies
|
O’Rourke, Patrick F.
|
|
|
193 |
C |
p.
|
artikel
|
| 39 |
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor
|
Umar, Efrizon
|
|
|
193 |
C |
p.
|
artikel
|
| 40 |
Transmutation study of 237Np in CiADS
|
Guo, Yuyao
|
|
|
193 |
C |
p.
|
artikel
|
| 41 |
Uncertainty analysis of the China experimental fast reactor start-up tests based on refined calculation results
|
Du, Xianan
|
|
|
193 |
C |
p.
|
artikel
|
| 42 |
Utilization of ACE nuclear data file toolkit ACEtk to calculate relative sensitivity coefficients of point-kinetics parameters
|
Kleedtke, Noah
|
|
|
193 |
C |
p.
|
artikel
|
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