| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accelerating the solution of the S N equations with highly anisotropic scattering using the Fokker-Planck approximation
|
Patel, Japan K.
|
|
|
147 |
C |
p.
|
artikel
|
| 2 |
A design of switching supervisory control based on fuzzy-PID controllers for VVER-1000 pressurizer system with RELAP5 and MATLAB coupling
|
Lotfi, Mohammad
|
|
|
147 |
C |
p.
|
artikel
|
| 3 |
Analysis of influencing factors of rupture phenomenon of liquid film on the wall of corrugated plate dryer
|
Wang, Bo
|
|
|
147 |
C |
p.
|
artikel
|
| 4 |
Analysis of the Kalinin-3 coolant transient benchmark by SKETCH-N/SKAZKA code system
|
Ojinnaka, Chukwudi A.S.
|
|
|
147 |
C |
p.
|
artikel
|
| 5 |
Analysis of the temperature distribution in the pin bundle of the CIRCE facility
|
Buzzi, F.
|
|
|
147 |
C |
p.
|
artikel
|
| 6 |
Arbitrary-level coarse mesh finite difference acceleration with hierarchical coarsening in space and energy
|
Hackemack, Michael W.
|
|
|
147 |
C |
p.
|
artikel
|
| 7 |
Availability analysis of safety-critical and control systems of NPP using stochastic modeling
|
Kumar, Pramod
|
|
|
147 |
C |
p.
|
artikel
|
| 8 |
Axial expansion for prompt safety of a small lead-cooled reactor
|
Zhang, You-Peng
|
|
|
147 |
C |
p.
|
artikel
|
| 9 |
Comparative study on water thermodynamic property functions of TRACE code
|
Zhong, Xianping
|
|
|
147 |
C |
p.
|
artikel
|
| 10 |
Comparison of machine learning models for the detection of partial defects in spent nuclear fuel
|
Rossa, Riccardo
|
|
|
147 |
C |
p.
|
artikel
|
| 11 |
Comparison of point reactor response and space-dependent core response
|
Anghel, V.N.P.
|
|
|
147 |
C |
p.
|
artikel
|
| 12 |
Consequence analysis of a postulated nuclear excursion in BWR spent fuel pool using 1/fβ spectrum model of randomization
|
Simanullang, Irwan Liapto
|
|
|
147 |
C |
p.
|
artikel
|
| 13 |
Development and assessment of adjoint sensitivity analysis method for transient two-phase flow simulations
|
Hu, Guojun
|
|
|
147 |
C |
p.
|
artikel
|
| 14 |
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
|
Chionis, D.
|
|
|
147 |
C |
p.
|
artikel
|
| 15 |
Editorial Board
|
|
|
|
147 |
C |
p.
|
artikel
|
| 16 |
Effectiveness analysis of hydrogen control system in AP1000 nuclear power plant under LB-LOCA
|
Lyu, Xuefeng
|
|
|
147 |
C |
p.
|
artikel
|
| 17 |
Enhancement of convective-diffusion limited vaporization rates of fission products by metal fog formation
|
Epstein, Michael
|
|
|
147 |
C |
p.
|
artikel
|
| 18 |
Evaluation of burnup calculation for double-heterogeneity system based on Sanchez-MOC framework in LWR
|
Zhang, Yunfei
|
|
|
147 |
C |
p.
|
artikel
|
| 19 |
Experimental study on single droplet impinging on a heated and inclined wall at early impaction stage
|
Tian, Wenlong
|
|
|
147 |
C |
p.
|
artikel
|
| 20 |
Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD analysis
|
Song, Min Seop
|
|
|
147 |
C |
p.
|
artikel
|
| 21 |
Graphite dust emission evaluation in an HTGR depressurization accident
|
Sun, Qi
|
|
|
147 |
C |
p.
|
artikel
|
| 22 |
Impact of corium thermophysical properties on fuel-coolant interaction
|
Brayer, Claude
|
|
|
147 |
C |
p.
|
artikel
|
| 23 |
Measurement uncertainty of rossi-alpha neutron experiments
|
Hua, Michael Y.
|
|
|
147 |
C |
p.
|
artikel
|
| 24 |
Minimum collective dose based optimal evacuation path-planning method under nuclear accidents
|
Pei, Qiu-Yan
|
|
|
147 |
C |
p.
|
artikel
|
| 25 |
Nuclear properties of Tungsten under 14 MeV neutron irradiation for fusion-fission hybrid reactors
|
García Gallardo, J.A.
|
|
|
147 |
C |
p.
|
artikel
|
| 26 |
Numerical method development for oxidation particle formation during sodium spray fires in SFR containment
|
Sun, Hongping
|
|
|
147 |
C |
p.
|
artikel
|
| 27 |
OECD/NRC PWR MOX/UO2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW
|
Ferraro, Diego
|
|
|
147 |
C |
p.
|
artikel
|
| 28 |
Parallelization and optimization of RMC for criticality computing based on the heterogeneous architecture of the Sunway TaihuLight supercomputer
|
Chen, Feiyu
|
|
|
147 |
C |
p.
|
artikel
|
| 29 |
Performance prediction of annular linear induction pump under constant slip frequency operation
|
Sharma, Prashant
|
|
|
147 |
C |
p.
|
artikel
|
| 30 |
Preliminary study of system design and safety analysis methodology for supercritical carbon dioxide Brayton cycle direct-cooled reactor system
|
Gao, Chuntian
|
|
|
147 |
C |
p.
|
artikel
|
| 31 |
Rapid accident source term estimation (RASTE) for nuclear emergency response in high temperature gas cooled reactor
|
Wang, Jiaxin
|
|
|
147 |
C |
p.
|
artikel
|
| 32 |
Reassessing methods to close the nuclear fuel cycle
|
Dixon, B.
|
|
|
147 |
C |
p.
|
artikel
|
| 33 |
Reduced order models in reactor kinetics: A comparison between point kinetics and multipoint kinetics
|
Valocchi, G.
|
|
|
147 |
C |
p.
|
artikel
|
| 34 |
Research of ring RPT method on spherical and cylindrical Double-Heterogeneous systems
|
Lou, Lei
|
|
|
147 |
C |
p.
|
artikel
|
| 35 |
Risk Analysis of Out-drum Mixing Cement Solidification by HAZOP and Risk Matrix
|
Wang, Rui
|
|
|
147 |
C |
p.
|
artikel
|
| 36 |
SCALE capabilities for high temperature gas-cooled reactor analysis
|
Bostelmann, Friederike
|
|
|
147 |
C |
p.
|
artikel
|
| 37 |
Sensitivity analysis of thermal-hydraulic models based on FFTBM-MSM two-layer method for PKL IBLOCA experiment
|
Xu, Hong
|
|
|
147 |
C |
p.
|
artikel
|
| 38 |
Stability and steady state analysis of control and safety systems of Nuclear Power Plants
|
Gupta, Brijendra
|
|
|
147 |
C |
p.
|
artikel
|
| 39 |
State feedback control of power in a small modular reactor
|
Zarei, M.
|
|
|
147 |
C |
p.
|
artikel
|
| 40 |
The importance of representative aerosol diameter and bubble size distribution in pool scrubbing
|
Kim, Yo Han
|
|
|
147 |
C |
p.
|
artikel
|
| 41 |
Theoretical study of steady-state characteristics of natural circulation system
|
Song, Gongle
|
|
|
147 |
C |
p.
|
artikel
|
| 42 |
The risk analysis of the electrical Cross-tie for extended Station Blackout in Multi-Unit site
|
Khamis Alsuwaidi, Jamila
|
|
|
147 |
C |
p.
|
artikel
|
| 43 |
Time-invariant reliability assessment for a passive heat removal system based on FORM methodology with a new approach for finding the design point
|
Ebrahimian, M.
|
|
|
147 |
C |
p.
|
artikel
|
| 44 |
Transient thermal–hydraulic analysis of SCO2-cooled reactor system with modified RELAP5
|
Zhang, Yuandong
|
|
|
147 |
C |
p.
|
artikel
|
| 45 |
Underwater laser cutting of stainless steel up to 100 mm thick for dismantling application in nuclear power plants
|
Shin, Jae Sung
|
|
|
147 |
C |
p.
|
artikel
|
| 46 |
Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation
|
Bao, Han
|
|
|
147 |
C |
p.
|
artikel
|
| 47 |
Validation of SARAX code system using the SFR operational tests
|
Du, Xianan
|
|
|
147 |
C |
p.
|
artikel
|
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