| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
An internal parallel coupling method based on NECP-X and CTF and analysis of the impact of thermal-hydraulic model to the high-fidelity calculations
|
Liu, Zhouyu
|
|
|
146 |
C |
p.
|
artikel
|
| 2 |
An online operator support tool for severe accident management in nuclear power plants using dynamic event trees and deep learning
|
Lee, Ji Hyun
|
|
|
146 |
C |
p.
|
artikel
|
| 3 |
Convergence characteristics and Wielandt acceleration of the time source method for Monte Carlo alpha eigenvalue calculations
|
Yamamoto, Toshihiro
|
|
|
146 |
C |
p.
|
artikel
|
| 4 |
Critical verification for TRX and BAPL benchmarks based on ENDF/B-VIII.0 using DRAGON code
|
Xiao, Xiang
|
|
|
146 |
C |
p.
|
artikel
|
| 5 |
Development of a new features selection algorithm for estimation of NPPs operating parameters
|
Moshkbar-Bakhshayesh, Khalil
|
|
|
146 |
C |
p.
|
artikel
|
| 6 |
Editorial Board
|
|
|
|
146 |
C |
p.
|
artikel
|
| 7 |
Effect of zinc addition on fuel crud deposition in simulated PWR primary coolant conditions
|
Kim, Kyeong-Su
|
|
|
146 |
C |
p.
|
artikel
|
| 8 |
Elaboration of a Phenomena Identification Ranking Table (PIRT) for the modelling of In-Vessel Retention
|
Fichot, F.
|
|
|
146 |
C |
p.
|
artikel
|
| 9 |
Experimental simulation of channel heat-up behaviour under slumped fuel pin condition for Indian PHWR
|
Ajay, Ketan
|
|
|
146 |
C |
p.
|
artikel
|
| 10 |
Implementation of the unscented transformation with low rank approximation in uncertainty analysis during large-break loss of coolant accident
|
Foad, Basma
|
|
|
146 |
C |
p.
|
artikel
|
| 11 |
Investigation of the chord length Markovian probability distribution for self-shielding treatment on double heterogeneity problem
|
Liang, Yuechao
|
|
|
146 |
C |
p.
|
artikel
|
| 12 |
Leakage estimation of the high-pressure and high-temperature natural circulation helium loop
|
Világi, František
|
|
|
146 |
C |
p.
|
artikel
|
| 13 |
Main outcomes from the IVR code benchmark performed in the European IVMR project
|
Carénini, L.
|
|
|
146 |
C |
p.
|
artikel
|
| 14 |
Massimo Salvatores 1941–2020
|
|
|
|
146 |
C |
p.
|
artikel
|
| 15 |
Neutron diffusion coefficient for disordered arrays of TRISO particles in spherical nuclear fuel
|
Aguilar-Madera, C.G.
|
|
|
146 |
C |
p.
|
artikel
|
| 16 |
PC-based JSI research reactor simulator
|
Malec, Jan
|
|
|
146 |
C |
p.
|
artikel
|
| 17 |
PIV measurements of the cross flow induced by a wrapped wire spacer
|
Wang, Han
|
|
|
146 |
C |
p.
|
artikel
|
| 18 |
Possibility to stabilize plutonium inventory in a sodium-cooled small modular reactors – Pressurized water reactors fleet
|
Tirel, K.
|
|
|
146 |
C |
p.
|
artikel
|
| 19 |
Potential tellurium deposits in the BWR containment during a severe nuclear accident
|
Espegren, Fredrik
|
|
|
146 |
C |
p.
|
artikel
|
| 20 |
Reliability and performance analysis of safety-critical system using transformation of UML into state space models
|
Mamdikar, Mohan Rao
|
|
|
146 |
C |
p.
|
artikel
|
| 21 |
Retrofitting of ex-vessel core catchers into operating nuclear power plants at the example of a Mark-I BWR
|
Fischer, Manfred
|
|
|
146 |
C |
p.
|
artikel
|
| 22 |
Review of thermophysical property methods applied to fueled and un-fueled molten salts
|
Magnusson, Jared
|
|
|
146 |
C |
p.
|
artikel
|
| 23 |
Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory
|
Introini, Carolina
|
|
|
146 |
C |
p.
|
artikel
|
| 24 |
Subchannel analysis of annular fuel assembly using the preconditioned Jacobian-free Newton Krylov methods
|
Esmaili, H.
|
|
|
146 |
C |
p.
|
artikel
|
| 25 |
The response matrix acceleration: A new non-linear method for the 3D discrete-ordinate transport equation
|
Ford, Wesley
|
|
|
146 |
C |
p.
|
artikel
|
| 26 |
Verification and validation tests of gamma library of MC2-3 for coupled neutron and gamma heating calculation
|
Park, H.
|
|
|
146 |
C |
p.
|
artikel
|
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