| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Acceleration of surface tracking in Monte Carlo transport via distance caching
|
Kowalski, Mikolaj Adam
|
|
|
152 |
C |
p.
|
artikel
|
| 2 |
A Collision-based Domain Decomposition scheme for large-scale depletion with the Serpent 2 Monte Carlo code
|
García, Manuel
|
|
|
152 |
C |
p.
|
artikel
|
| 3 |
A multiscale approach to analyze the effect of radial void fraction distributions on BWR neutronic lattice parameters
|
Price, Dean
|
|
|
152 |
C |
p.
|
artikel
|
| 4 |
Analysis of gas-cooled fast reactor integral shielding experiment: “Wuerenlingen iron benchmark experiment (PROTEUS)” using SuperMC
|
Baidoo, Isaac Kwasi
|
|
|
152 |
C |
p.
|
artikel
|
| 5 |
Analysis of neutron physics and thermal hydraulics for fuel assembly of small modular reactor loaded with ATFs
|
Yu, Honghao
|
|
|
152 |
C |
p.
|
artikel
|
| 6 |
Analysis of physical protection system effectiveness of nuclear power plants based on performance approach
|
Cheikh El Wely, I.
|
|
|
152 |
C |
p.
|
artikel
|
| 7 |
Analysis of the natural circulation test of PHENIX reactor by the THACS code
|
Liu, Yapeng
|
|
|
152 |
C |
p.
|
artikel
|
| 8 |
An efficient numerical method for fractional neutron diffusion equation in the presence of different types of reactivities
|
Roul, Pradip
|
|
|
152 |
C |
p.
|
artikel
|
| 9 |
A neutron field reconstruction method for reactor based on semi-supervised learning
|
Cao, Pei
|
|
|
152 |
C |
p.
|
artikel
|
| 10 |
An investigation of pressure build-up effects due to check valve’s closing characteristics using dynamic mesh techniques of CFD
|
Kim, Nam-Seok
|
|
|
152 |
C |
p.
|
artikel
|
| 11 |
Application of a severe accident code to the sensitivity and uncertainty analysis of hydrogen production in the WWER1000/V446
|
Gharari, R.
|
|
|
152 |
C |
p.
|
artikel
|
| 12 |
A review of the scientific contributions by Massimo Salvatores to nuclear reactor physics and engineering
|
Palmiotti, Giuseppe
|
|
|
152 |
C |
p.
|
artikel
|
| 13 |
A systematic process for developing fire scenarios in risk assessment for nuclear power plants
|
Hsu, Pi-Lin
|
|
|
152 |
C |
p.
|
artikel
|
| 14 |
Computational studies on pressurized thermal shock in reactor pressure vessel
|
Chouhan, Rakesh
|
|
|
152 |
C |
p.
|
artikel
|
| 15 |
Coupled CLASS and DONJON5 3D full-core calculations and comparison with the neural network approach for fuel cycles involving MOX fueled PWRs
|
Guillet, Martin
|
|
|
152 |
C |
p.
|
artikel
|
| 16 |
Depletion capabilities in the OpenMC Monte Carlo particle transport code
|
Romano, Paul K.
|
|
|
152 |
C |
p.
|
artikel
|
| 17 |
Design of enhanced air-cooled natural circulation systems assisted by thermoelectric generator and analysis of effectiveness and enhancement mechanism
|
Wang, Dongqing
|
|
|
152 |
C |
p.
|
artikel
|
| 18 |
Development of a thermal-hydraulic analysis code for primary system of an integrated small modular pressurized water reactor
|
Wang, Dongqing
|
|
|
152 |
C |
p.
|
artikel
|
| 19 |
Distributed parameter modeling for the steam generator in the nuclear power plant
|
Hui, Jiuwu
|
|
|
152 |
C |
p.
|
artikel
|
| 20 |
Editorial Board
|
|
|
|
152 |
C |
p.
|
artikel
|
| 21 |
Estimating buildup factor of alloys based on combination of Monte Carlo method and multilayer feed-forward neural network
|
Moshkbar-Bakhshayesh, Khalil
|
|
|
152 |
C |
p.
|
artikel
|
| 22 |
Evaluation of ATFs in core degradation of a PWR in unmitigated SBLOCA
|
Ebrahimgol, H.
|
|
|
152 |
C |
p.
|
artikel
|
| 23 |
Evaluation of nanofluid coolant effects on VVER-1000/V-446 reactor using 3-D full core coupled neutronic and thermohydraulics analysis
|
Saadati, Hassan
|
|
|
152 |
C |
p.
|
artikel
|
| 24 |
Experimental study on flow distribution and mixing at the core inlet of double-loop small module reactor
|
Peng, Fan
|
|
|
152 |
C |
p.
|
artikel
|
| 25 |
Implementation of a microstructural densification model in the DIONISIO nuclear fuel simulation code
|
Cazado, Mauricio E.
|
|
|
152 |
C |
p.
|
artikel
|
| 26 |
Improved MPACT energy deposition and explicit heat generation coupling with CTF
|
Liu, Yuxuan
|
|
|
152 |
C |
p.
|
artikel
|
| 27 |
Investigation of in-beam prompt and delayed neutron counting techniques for detection and characterization of special nuclear material
|
Bentoumi, G.
|
|
|
152 |
C |
p.
|
artikel
|
| 28 |
Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions
|
Bieder, U.
|
|
|
152 |
C |
p.
|
artikel
|
| 29 |
Investigation of the continuum-rarefied flow and isotope separation using a hybrid CFD-DSMC simulation for U F 6 in a gas centrifuge
|
Ghazanfari, Valiyollah
|
|
|
152 |
C |
p.
|
artikel
|
| 30 |
MAAP5 simulation of AP1000 severe accident induced by pressurizer safety valve stuck-open
|
Wang, Meng
|
|
|
152 |
C |
p.
|
artikel
|
| 31 |
Measurement of void fraction in pipes by nuclear transmission based techniques
|
Osman, A.M.
|
|
|
152 |
C |
p.
|
artikel
|
| 32 |
Modelling and analysis of extra vessel electro magnetic pump for a small modular lead-bismuth fast reactor
|
Kwak, Jaesik
|
|
|
152 |
C |
p.
|
artikel
|
| 33 |
Modelling of fission products release in VERDON-1 experiment with cGEMS: Coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
|
Nichenko, Sergii
|
|
|
152 |
C |
p.
|
artikel
|
| 34 |
Multidimensional prediction of the effect of flow blockage in SCTF S1-01 experiment using MARS-KS code
|
Bang, Young Seok
|
|
|
152 |
C |
p.
|
artikel
|
| 35 |
Neutronic design and dynamic analysis of a 450 MWth graphite molten salt reactor core
|
Xie, Jinsen
|
|
|
152 |
C |
p.
|
artikel
|
| 36 |
Potential radiological hazard and options to cope with consequences from recycling of activated metal waste disposed of at a near-surface disposal facility
|
Lee, Wang Hyeon
|
|
|
152 |
C |
p.
|
artikel
|
| 37 |
Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
|
Ashraf, O.
|
|
|
152 |
C |
p.
|
artikel
|
| 38 |
Preliminary feasibility study of PCM condenser for PCCS of APR1400
|
Cho, Jai Oan
|
|
|
152 |
C |
p.
|
artikel
|
| 39 |
Research and development of a transient thermal–hydraulic code for system safety analysis of sodium cooled fast reactor
|
Yu, Yang
|
|
|
152 |
C |
p.
|
artikel
|
| 40 |
Solution-dependent predictor-corrector flux mapping algorithm for discrete ordinates calculation on multilevel discontinuous grids
|
Liu, Cong
|
|
|
152 |
C |
p.
|
artikel
|
| 41 |
Study on the CHF correction factor under rolling condition in vertical tube
|
Liu, Yang
|
|
|
152 |
C |
p.
|
artikel
|
| 42 |
The analysis of density wave instability phenomena of supercritical water in two parallel channels
|
Zang, Jinguang
|
|
|
152 |
C |
p.
|
artikel
|
| 43 |
The application of high fidelity reactor simulation on Cobalt-59 activation calculation
|
Cai, Li
|
|
|
152 |
C |
p.
|
artikel
|
| 44 |
The station blackout accident in a dual-cooled annular fuel of a VVER-1000 reactor with application of portable pumps for mitigating the accident
|
Mehri, A.M.
|
|
|
152 |
C |
p.
|
artikel
|
| 45 |
Validation of CFD code FLUIDYN-MP for steam condensation at walls in presence of non-condensable gases
|
Gera, B.
|
|
|
152 |
C |
p.
|
artikel
|
| 46 |
Validation of the Monte Carlo code MONK for thermal 232Th/233U systems using the JEF-2.2 and JEFF-3.1 libraries
|
Peakman, Aiden
|
|
|
152 |
C |
p.
|
artikel
|
| 47 |
Vortex-ring-induced elliptical drop deformation process in ambient liquid under an impact: The effects of the drop shape and other parameters
|
Liao, Bin
|
|
|
152 |
C |
p.
|
artikel
|
| 48 |
Zero-power noise up to 100 kHz in the IPEN/MB-01 research reactor facility
|
Feliciano dos Santos, Diogo
|
|
|
152 |
C |
p.
|
artikel
|
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