| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A cumulative damage model for tubes in nuclear power plants subject to continuous degradation and multi-effect shocks under dynamic environments
|
Xie, Xiwen
|
|
|
209 |
C |
p.
|
artikel
|
| 2 |
A fuzzy-based AHP-VIKOR framework for risk analysis of safety-critical systems: A case study of nuclear power plant
|
Das, Anwesa
|
|
|
209 |
C |
p.
|
artikel
|
| 3 |
A Hankel Transform approach to Doppler broadening
|
Gert, Godfree
|
|
|
209 |
C |
p.
|
artikel
|
| 4 |
Assessment of wall models for coarse-mesh RANS simulations
|
Fogliatto, Ezequiel
|
|
|
209 |
C |
p.
|
artikel
|
| 5 |
Consideration of Cr-doped UO 2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept
|
de Lara, A.
|
|
|
209 |
C |
p.
|
artikel
|
| 6 |
CORTEX experiments, Part III: Experimental determination of the zero power transfer function of AKR-2 with reliable uncertainties
|
Knospe, Alexander
|
|
|
209 |
C |
p.
|
artikel
|
| 7 |
Development and verification of multigroup advanced semi analytic nodal method solver for HTGR analysis with MHTGR-350
|
Jang, Jaerim
|
|
|
209 |
C |
p.
|
artikel
|
| 8 |
Editorial Board
|
|
|
|
209 |
C |
p.
|
artikel
|
| 9 |
Effect of alkaline solution on hydraulic and mechanical properties of MX80 granular bentonite
|
Shao, Jiesheng
|
|
|
209 |
C |
p.
|
artikel
|
| 10 |
Experimental study on 100 hour-term performance of high-temperature sodium heat pipes
|
Su, Zilin
|
|
|
209 |
C |
p.
|
artikel
|
| 11 |
Influence of staggered guide vane on hydraulic performance of reactor coolant pump
|
Liu, Binhao
|
|
|
209 |
C |
p.
|
artikel
|
| 12 |
Mode-driven explainable artificial intelligence approach for estimating background radiation spectrum in a measurement applicable to nuclear security
|
Alamaniotis, Miltiadis
|
|
|
209 |
C |
p.
|
artikel
|
| 13 |
Modeling and flux reconstruction of unstructured geometric reactor
|
Xiao, Bowen
|
|
|
209 |
C |
p.
|
artikel
|
| 14 |
Multi-objective optimization of a PWR core loading pattern by backtracking search algorithm
|
Nasir, Rubina
|
|
|
209 |
C |
p.
|
artikel
|
| 15 |
Neutronic calculations for preliminary core design of SCW-SMR
|
Antók, Csenge
|
|
|
209 |
C |
p.
|
artikel
|
| 16 |
Numerical study on benchmark analysis of NACIE-UP facility with uniform and non-uniform power distribution
|
Li, Haoyang
|
|
|
209 |
C |
p.
|
artikel
|
| 17 |
R2CA H2020 project for Reduction of Radiological Consequences of design basis and design extension Accidents
|
|
|
|
209 |
C |
p.
|
artikel
|
| 18 |
Research on influence of wear ring clearance on energy loss of reactor coolant pump
|
Long, Yun
|
|
|
209 |
C |
p.
|
artikel
|
| 19 |
Scale effects on core design, fuel costs, and spent fuel volume of pressurized water reactors
|
Halimi, Assil
|
|
|
209 |
C |
p.
|
artikel
|
| 20 |
Searching for optimum design and burnable absorber for controlling the reactivity of U.S. Supper critical water reactor (SCWR)
|
Alnassar, Nassar
|
|
|
209 |
C |
p.
|
artikel
|
| 21 |
Simulation study on the transient operating characteristics of equal height difference passive containment cooling system
|
Zhao, Quanbin
|
|
|
209 |
C |
p.
|
artikel
|
| 22 |
Study on the specifications of the basic core configurations of the modified STACY
|
Gunji, Satoshi
|
|
|
209 |
C |
p.
|
artikel
|
| 23 |
Theoretical models validation of Cr -51 production reactions for medical applications
|
Saad, Maher T.
|
|
|
209 |
C |
p.
|
artikel
|
| 24 |
Thermal-hydraulic performance and safety assessment of an LBE-cooled reactor under steady-state and unprotected transients
|
Hashim, Muhammad
|
|
|
209 |
C |
p.
|
artikel
|
| 25 |
Towards early detection of model conflicts in the design of the MYRRHA reactor in a systems engineering approach
|
De Florio, Vincenzo
|
|
|
209 |
C |
p.
|
artikel
|
| 26 |
Using a surrogate model for the detection of defective PWR fuel rods
|
Chevalier-Jabet, Karine
|
|
|
209 |
C |
p.
|
artikel
|
| 27 |
Validation and parametric study of FFRD model in DRACCAR code
|
Choi, Chiwoong
|
|
|
209 |
C |
p.
|
artikel
|
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