| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Adjustment of group cross sections by means of integral data (ENDF/-VII.1)
|
Makhloul, M.
|
|
|
118 |
C |
p.
|
artikel
|
| 2 |
A fast and robust Bayesian update of components failure rates in a nuclear power plant
|
Ayoub, Ali
|
|
|
118 |
C |
p.
|
artikel
|
| 3 |
Aggregates grain size and press rate dependence of the shielding parameters for some concretes
|
Mahmoud, K.A.
|
|
|
118 |
C |
p.
|
artikel
|
| 4 |
Analysis of flow and heat transfer through a partially blocked fuel subassembly of fast breeder reactor
|
Sarkar, Madhusree
|
|
|
118 |
C |
p.
|
artikel
|
| 5 |
A new fuel depletion code based on group-wised energy Bateman ODEs; SUDEPLET code for point-like PWR core
|
Faghihi, F.
|
|
|
118 |
C |
p.
|
artikel
|
| 6 |
A possible application of catastrophe theory to boiling water reactor instability
|
Pázsit, Imre
|
|
|
118 |
C |
p.
|
artikel
|
| 7 |
Application of integrated microgrid for strengthening the station blackout power supply in nuclear power plant
|
Khatua, Subhakanta
|
|
|
118 |
C |
p.
|
artikel
|
| 8 |
Benchmark of DEMAIN, a new calculation package for decommissioning purposes
|
Le Loirec, C.
|
|
|
118 |
C |
p.
|
artikel
|
| 9 |
Comparison of semi-heavy water and H2O as coolant for a conceptual research reactor from the view point of neutronic parameters
|
Rahimi, Ghasem
|
|
|
118 |
C |
p.
|
artikel
|
| 10 |
Conceptual core design study for Indonesian Space Reactor (ISR)
|
Khandaq, Muhammad Farid
|
|
|
118 |
C |
p.
|
artikel
|
| 11 |
Correlations for friction factor of turbulent pipe flow under supercritical pressure: Review and a new correlation
|
Fang, Xiande
|
|
|
118 |
C |
p.
|
artikel
|
| 12 |
Corrosion behavior of base metal and weld bead of CLAM steel in flowing Pb-Bi at 550 °C
|
Chen, Gang
|
|
|
118 |
C |
p.
|
artikel
|
| 13 |
Current achievements on bubble dynamics analysis using MPS method
|
Chen, Ronghua
|
|
|
118 |
C |
p.
|
artikel
|
| 14 |
Decoupling header steam pressure control strategy in Multi-Reactor and Multi-Load Nuclear Power Plant
|
Nuerlan, Areai
|
|
|
118 |
C |
p.
|
artikel
|
| 15 |
Development of a Deep Rectifier Neural Network for dose prediction in nuclear emergencies with radioactive material releases
|
Desterro, Filipe S.M.
|
|
|
118 |
C |
p.
|
artikel
|
| 16 |
Development of reverse meshing technology on geometry reconstruction for CFD code GASFLOW-MPI
|
Yu, Fujiang
|
|
|
118 |
C |
p.
|
artikel
|
| 17 |
Diffusion layer model for condensation of vapor with the presence of noncondensable gas under natural convective condensation
|
Lu, Junhui
|
|
|
118 |
C |
p.
|
artikel
|
| 18 |
Economic feasibility of flexible energy productions by small modular reactors from the perspective of integrated planning
|
Nian, Victor
|
|
|
118 |
C |
p.
|
artikel
|
| 19 |
Editorial Board
|
|
|
|
118 |
C |
p.
|
artikel
|
| 20 |
Entropy generation study for a supercritical water reactor (SCWR)
|
Valujerdi, M.M.
|
|
|
118 |
C |
p.
|
artikel
|
| 21 |
Evaluation of an aerodynamic barrier approach to limit the dispersion of fission products in the event of containment failure
|
Ullah, Sana
|
|
|
118 |
C |
p.
|
artikel
|
| 22 |
Evaluation of gamma-ray and neutron shielding features of heavy metals doped Bi2O3-BaO-Na2O-MgO-B2O3 glass systems
|
Sayyed, M.I.
|
|
|
118 |
C |
p.
|
artikel
|
| 23 |
Evaluation of neutron radiation damage in zircaloy fuel clad of nuclear power plants: a study based on PKA and dpa calculations
|
Noori-kalkhoran, Omid
|
|
|
118 |
C |
p.
|
artikel
|
| 24 |
Experimental measurements and theoretical simulation of sodium combustion aerosol leakage through capillaries
|
Narayanam, Sujatha Pavan
|
|
|
118 |
C |
p.
|
artikel
|
| 25 |
Experimental measurements of isothermal reactivity coefficient and temperature-dependent reactivity changes with associated uncertainty evaluations
|
Dupont, Mathieu N.
|
|
|
118 |
C |
p.
|
artikel
|
| 26 |
Experimental research on fragmentation characteristics of molten stainless steel discharged into sodium pool and comparison with molten copper
|
Hu, Liang
|
|
|
118 |
C |
p.
|
artikel
|
| 27 |
Experimental study on transient performance of heat pipe-cooled passive residual heat removal system of a molten salt reactor
|
Wang, Chenglong
|
|
|
118 |
C |
p.
|
artikel
|
| 28 |
Extended development of a Monte Carlo code OpenMC for fuel cycle simulation of molten salt reactor
|
Zhuang, Kun
|
|
|
118 |
C |
p.
|
artikel
|
| 29 |
Full-scale numerical study on the flow characteristics and mal-distribution phenomena in SG steam-water separation system of an advanced PWR
|
Fang, Di
|
|
|
118 |
C |
p.
|
artikel
|
| 30 |
Full-scale numerical study on the thermal-hydraulic characteristics of steam-water separation system in an advanced PWR UTSG. Part two: Droplets separation process
|
Fang, Di
|
|
|
118 |
C |
p.
|
artikel
|
| 31 |
Increasing efficiency of nuclear fuel using burnable absorbers
|
Lovecký, M.
|
|
|
118 |
C |
p.
|
artikel
|
| 32 |
Investigation of the chance structure of the fission cross section of 238U by neutrons in energy range from 14 to 18 Mev using the delayed neutrons
|
Gremyachkin, D.E.
|
|
|
118 |
C |
p.
|
artikel
|
| 33 |
Investigation on the effect of 238U replacement with 232Th in small modular reactor (SMR) fuel matrix
|
Uguru, Edwin Humphrey
|
|
|
118 |
C |
p.
|
artikel
|
| 34 |
Liquid low-level radioactive wastes treatment by using hydrophobized track-etched membranes
|
Zdorovets, M.V.
|
|
|
118 |
C |
p.
|
artikel
|
| 35 |
Machine-learning based error prediction approach for coarse-grid Computational Fluid Dynamics (CG-CFD)
|
Hanna, Botros N.
|
|
|
118 |
C |
p.
|
artikel
|
| 36 |
Matrix effects corrections in prompt gamma-ray spectra of a PGNAA online analyzer system using artificial neural network
|
Shahabinejad, Hadi
|
|
|
118 |
C |
p.
|
artikel
|
| 37 |
Modeling the short-term and long-term behaviour of the Oklo natural nuclear reactor phenomenon
|
Ibekwe, R.T.
|
|
|
118 |
C |
p.
|
artikel
|
| 38 |
Novel fault diagnosis scheme utilizing deep learning networks
|
Saeed, Hanan A.
|
|
|
118 |
C |
p.
|
artikel
|
| 39 |
( α ,n) reactions in oxide compounds calculated from the R-matrix theory
|
Pigni, M.T.
|
|
|
118 |
C |
p.
|
artikel
|
| 40 |
Numerical simulation of zircaloy-water reaction based on the moving particle semi-implicit method and combined analysis with the MIDAC code for the nuclear-reactor core melting process
|
Wang, Dong
|
|
|
118 |
C |
p.
|
artikel
|
| 41 |
On a point kinetic model for nuclear reactors considering the variation in fuel composition
|
Paganin, T.M.
|
|
|
118 |
C |
p.
|
artikel
|
| 42 |
On the study of microstructure of annealed C+and H2 + Co_implanted 6H-SiC
|
Ye, Chao
|
|
|
118 |
C |
p.
|
artikel
|
| 43 |
Physics conditions of passive autonomous frequency control operation in conventional large-size PWRs
|
Abdelhameed, Ahmed Amin E.
|
|
|
118 |
C |
p.
|
artikel
|
| 44 |
Potential of the submerged plant Myriophyllum spicatum for treatment of aquatic environments contaminated with stable or radioactive cobalt and cesium
|
Saleh, Hosam M.
|
|
|
118 |
C |
p.
|
artikel
|
| 45 |
Providing support to operators for monitoring safety functions using reinforcement learning
|
Park, JaeKwan
|
|
|
118 |
C |
p.
|
artikel
|
| 46 |
RADCOM: Radiation dose computation model- a software for radiological impact assessment
|
Rout, Sabyasachi
|
|
|
118 |
C |
p.
|
artikel
|
| 47 |
Radiological assessment on spent resin treatment facility and transportation for radioactive waste disposal
|
Choi, Woo Nyun
|
|
|
118 |
C |
p.
|
artikel
|
| 48 |
Radionuclide distribution during ytterbium doped fibre laser cutting for nuclear decommissioning
|
Dodds, Jonathan M.
|
|
|
118 |
C |
p.
|
artikel
|
| 49 |
Reconstruction of the neutron radiation field on nuclear facilities near the shield using Bayesian inference
|
Wang, Zhuang
|
|
|
118 |
C |
p.
|
artikel
|
| 50 |
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method
|
Vergari, Lorenzo
|
|
|
118 |
C |
p.
|
artikel
|
| 51 |
Research on radionuclide migration in coastal waters under nuclear leakage accident
|
Li, Zichao
|
|
|
118 |
C |
p.
|
artikel
|
| 52 |
Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants
|
Cheng, Wen-Chi
|
|
|
118 |
C |
p.
|
artikel
|
| 53 |
Richardson number criteria for direct-contact-condensation-induced thermal stratification using visualization
|
Jo, Byeongnam
|
|
|
118 |
C |
p.
|
artikel
|
| 54 |
Role of aluminum and silicon species in the formation of hard sludge on the secondary side of PWR steam generators: Potential geopolymers contribution
|
Fernández-Saavedra, Rocío
|
|
|
118 |
C |
p.
|
artikel
|
| 55 |
Russian experimental database for validation of computer codes used for safety analysis of nuclear facilities
|
Zabirov, A.R.
|
|
|
118 |
C |
p.
|
artikel
|
| 56 |
Simplified virtual reality training system for radiation shielding and measurement in nuclear engineering
|
Hagita, Katsumi
|
|
|
118 |
C |
p.
|
artikel
|
| 57 |
Simulated studies on optimization and characterization of feed and product of melter for safe disposal of high-level radioactive liquid waste
|
Selvakumar, J.
|
|
|
118 |
C |
p.
|
artikel
|
| 58 |
Simulation of separative gaseous molecular flow through porous membrane with DSMC method
|
Abedi Masir, M.
|
|
|
118 |
C |
p.
|
artikel
|
| 59 |
Study of qualification process for sub-components of terminal service box
|
Zheng, Wangwang
|
|
|
118 |
C |
p.
|
artikel
|
| 60 |
Theoretical investigations on the U2Mo3Si4 compound from first-principles calculations
|
Song, Jiexi
|
|
|
118 |
C |
p.
|
artikel
|
| 61 |
Thermal footprint of a geological disposal facility containing EURO-GANEX wasteforms
|
Hsieh, Yun-Hao
|
|
|
118 |
C |
p.
|
artikel
|
| 62 |
Thermal-hydraulic analyses of MIT reactor LEU transition cycles
|
Dave, Akshay J.
|
|
|
118 |
C |
p.
|
artikel
|
| 63 |
To the special issue: Nonlinear nuclear reactor stability analysis and special aspects of modelling of complex dynamical systems (principles of model order reduction). Special issue on nonlinear stability analysis
|
Hennig, Dieter
|
|
|
118 |
C |
p.
|
artikel
|
| 64 |
Two-person game model of long-term safeguards for a final repository for spent nuclear fuel
|
Ju, Heejae
|
|
|
118 |
C |
p.
|
artikel
|
| 65 |
Two-phase flow void fraction estimation based on bubble image segmentation using Randomized Hough Transform with Neural Network (RHTN)
|
Serra, Pedro L.S.
|
|
|
118 |
C |
p.
|
artikel
|
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