| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A continuous learning monitoring strategy for multi-condition of nuclear power plant
|
Yu, Yue
|
|
|
164 |
C |
p.
|
artikel
|
| 2 |
A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system
|
Han, Zichao
|
|
|
164 |
C |
p.
|
artikel
|
| 3 |
Application of a BEPU-based code assessment to the ATLAS upper head SB-LOCA test
|
Al-Awad, Abdulrahman S.
|
|
|
164 |
C |
p.
|
artikel
|
| 4 |
A robust strategy for sensor fault detection in nuclear power plants based on principal component analysis
|
Zhu, Shaomin
|
|
|
164 |
C |
p.
|
artikel
|
| 5 |
A Source-expansion-based method for transient Pin-Power reconstruction
|
Bai, Jiahe
|
|
|
164 |
C |
p.
|
artikel
|
| 6 |
Burnup and neutronic analysis for UOX and MOX fuel assemblies in VVER reactor
|
Louis, Heba K.
|
|
|
164 |
C |
p.
|
artikel
|
| 7 |
CFD investigation for a 7-pin wrapped-wire fuel assembly with different wires
|
Lin, Junjie
|
|
|
164 |
C |
p.
|
artikel
|
| 8 |
CFD modelling of mixing vane spacer grids for ALLEGRO relevant gas cooled reactor fuel geometry
|
Orosz, Gergely Imre
|
|
|
164 |
C |
p.
|
artikel
|
| 9 |
Development and verification of the mathematical modeling for gas-pressurizer system
|
Shoghi, Abolfazl
|
|
|
164 |
C |
p.
|
artikel
|
| 10 |
Development of computer code ADWITA and data library for the solution of transmutation chain equations and application to the analysis of nuclear fuel cycles
|
Raj, Devesh
|
|
|
164 |
C |
p.
|
artikel
|
| 11 |
Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor
|
Zhang, K.
|
|
|
164 |
C |
p.
|
artikel
|
| 12 |
Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part II: DVI line small-break LOCA in CAP1400
|
Gao, Pengcheng
|
|
|
164 |
C |
p.
|
artikel
|
| 13 |
Editorial Board
|
|
|
|
164 |
C |
p.
|
artikel
|
| 14 |
Effects of the 3-D wall structures on the flow and mixing characteristics of pebbles in pebble beds in HTR-10
|
Li, Bin
|
|
|
164 |
C |
p.
|
artikel
|
| 15 |
Eigenvalue separation and eigenmode analysis by matrix-filling Monte Carlo methods
|
Vitali, Vito
|
|
|
164 |
C |
p.
|
artikel
|
| 16 |
Energy-based fault detection and isolation of a Brayton cycle-based HTGR power conversion unit – A comparative study
|
Neser, H.
|
|
|
164 |
C |
p.
|
artikel
|
| 17 |
Estimation of reactivity feedback and determination of safety criteria of inherent-safety fast reactors in unprotected transients based on the asymptotic approximation
|
Takeda, Toshikazu
|
|
|
164 |
C |
p.
|
artikel
|
| 18 |
Evidence-based background for constrained uncertainty quantification in a core transient analysis
|
Ivanov, Evgeny
|
|
|
164 |
C |
p.
|
artikel
|
| 19 |
Experimental investigation of turbulent flow under different Reynolds numbers and blockage ratios in a heated rectangular channel
|
Yuan, Dongdong
|
|
|
164 |
C |
p.
|
artikel
|
| 20 |
Experimentally investigating bubble dynamics and pressure drop for bubbly upflow in a vertical annular channel
|
Hsu, C.Y.
|
|
|
164 |
C |
p.
|
artikel
|
| 21 |
Experimental research of geometrical parameters influencing factor on fuel assembly mixing characteristics
|
Cheng, Cheng
|
|
|
164 |
C |
p.
|
artikel
|
| 22 |
Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor
|
Zhang, Qi
|
|
|
164 |
C |
p.
|
artikel
|
| 23 |
Experimental validation of DEMAIN for predicting induced radioactivity in research testing reactor civil engineering
|
Ritter, Guillaume
|
|
|
164 |
C |
p.
|
artikel
|
| 24 |
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors
|
Abrate, Nicolò
|
|
|
164 |
C |
p.
|
artikel
|
| 25 |
Improvement of evaluation of the contact pressure upon the penetration of a reactor lower head during a severe accident: Part 1. Conceptualization considering elastic deformation
|
Lim, Kukhee
|
|
|
164 |
C |
p.
|
artikel
|
| 26 |
Information content of integral experiments data: A Bayesian approach for quality assurance
|
Ivanov, Evgeny
|
|
|
164 |
C |
p.
|
artikel
|
| 27 |
Making sense of uncertain nuclear data
|
Talou, Patrick
|
|
|
164 |
C |
p.
|
artikel
|
| 28 |
Measurement of HFETR reactor power by improved 16N gamma spectrum analysis method
|
Lei, Ming
|
|
|
164 |
C |
p.
|
artikel
|
| 29 |
Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code
|
Rintala, Antti
|
|
|
164 |
C |
p.
|
artikel
|
| 30 |
Modeling of flow coastdown transient of a reactor coolant system under different pump failures
|
El-Sahlamy, Neama M.
|
|
|
164 |
C |
p.
|
artikel
|
| 31 |
Monte Carlo simulations of the water draining experimentof Giacint critical assembly
|
Cao, Yan
|
|
|
164 |
C |
p.
|
artikel
|
| 32 |
New feature of DARWIN/PEPIN2 inventory code: Propagation of nuclear data uncertainties to decay heat and nuclide density
|
Tsilanizara, A.
|
|
|
164 |
C |
p.
|
artikel
|
| 33 |
Nuclear criticality calculations using Geant4
|
Seghour, A.
|
|
|
164 |
C |
p.
|
artikel
|
| 34 |
On the simulation of neutron noise using a discrete ordinates method
|
Yi, Huaiqian
|
|
|
164 |
C |
p.
|
artikel
|
| 35 |
Performance analysis of PRHRS in primary and secondary circuit for offshore floating nuclear plant
|
Ma, Yichao
|
|
|
164 |
C |
p.
|
artikel
|
| 36 |
Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic
|
Zhang, K.
|
|
|
164 |
C |
p.
|
artikel
|
| 37 |
Realistic evaluation of source terms for steam generator tube rupture accidents
|
Shin, Hoyoung
|
|
|
164 |
C |
p.
|
artikel
|
| 38 |
Reduction of the source term of an assumed criticality accident in a fuel fabrication facility with solution system
|
Fukaya, Yuji
|
|
|
164 |
C |
p.
|
artikel
|
| 39 |
Remarks and improvements on neutron KERMA factors and radiation damage cross sections calculated by NECP-Atlas and NJOY21 using different evaluated nuclear data libraries
|
Yin, Wen
|
|
|
164 |
C |
p.
|
artikel
|
| 40 |
Research on the clearance flow between stator and rotor cans in canned motor RCP
|
Xu, Rui
|
|
|
164 |
C |
p.
|
artikel
|
| 41 |
Scaling analysis of the hydraulic behavior in reactor pressure vessel
|
Wang, L.S.
|
|
|
164 |
C |
p.
|
artikel
|
| 42 |
Scaling analysis of the thermal hydraulic behavior in the secondary side of steam generator
|
Wang, L.S.
|
|
|
164 |
C |
p.
|
artikel
|
| 43 |
Serpent transient analyses of GIACINT geometrical change experiments
|
Talamo, Alberto
|
|
|
164 |
C |
p.
|
artikel
|
| 44 |
Site-targeted evaluation of SWIFT-RIMPUFF for local-scale air dispersion modeling around Sanmen nuclear power plant based on multi-scenario wind tunnel experiments
|
Dong, Xinwen
|
|
|
164 |
C |
p.
|
artikel
|
| 45 |
Solving variable-coefficient burnup equations by exponential Rosenbrock methods
|
Xia, Shaopeng
|
|
|
164 |
C |
p.
|
artikel
|
| 46 |
Studies on the optimal mitigation strategy of extended SBO for the isolated multi-unit NPP site
|
Alsuwaidi, Jamila Khamis
|
|
|
164 |
C |
p.
|
artikel
|
| 47 |
Tellurium retention by containment spray system
|
Kärkelä, Teemu
|
|
|
164 |
C |
p.
|
artikel
|
| 48 |
Transient structural load characteristics of reactor coolant pump rotor system in rotor seizure accident
|
Lu, Yonggang
|
|
|
164 |
C |
p.
|
artikel
|
| 49 |
Two-zone stratified wetwell model development and implementation for RELAP-7
|
Cavaluzzi, Jack
|
|
|
164 |
C |
p.
|
artikel
|
| 50 |
Validation of photoneutron signals during CANDU reactor defuelling
|
Donnelly, J.V.
|
|
|
164 |
C |
p.
|
artikel
|
| 51 |
Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13
|
Wang, Shibao
|
|
|
164 |
C |
p.
|
artikel
|
| 52 |
Verification of multiphysics coupling techniques for modeling of molten salt reactors
|
Groth-Jensen, J.
|
|
|
164 |
C |
p.
|
artikel
|
| 53 |
WPEC Subgroup 44 computational Inter-comparison exercise on correlations in nuclear data libraries
|
Sobes, Vladimir
|
|
|
164 |
C |
p.
|
artikel
|
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