| no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
| 1 |
Adaptive Neuro-Fuzzy Inference System (ANFIS) based modelling of incipient steam generator tube rupture diagnosis
|
Mwaura, Anselim Mwangi
|
|
|
157 |
C |
p.
|
article
|
| 2 |
A mini-review on population balance model for gas-liquid subcooled boiling flow in nuclear industry
|
Hu, Guang
|
|
|
157 |
C |
p.
|
article
|
| 3 |
Analysis of the Power and Temperature distribution in molten salt reactors with TRACE. Application to the MSRE
|
Hanusek, Tomasz
|
|
|
157 |
C |
p.
|
article
|
| 4 |
Analysis of the TRAPU irradiation in PHENIX with TRIPOLI-4® and DARWIN-3 for the validation of fast reactor fuel depletion calculations
|
Calame, Aurélie
|
|
|
157 |
C |
p.
|
article
|
| 5 |
An approach to the experimental validation of the fission multiplying blanket of hybrid fusion fission systems
|
Salvatores, M.
|
|
|
157 |
C |
p.
|
article
|
| 6 |
An efficient and fast method to calculate integral experimental correlation coefficients – S2Cor
|
Sommer, Fabian
|
|
|
157 |
C |
p.
|
article
|
| 7 |
An efficient Dijkstra’s semaphore based k -out-of- n Petri net voting model: An application to shutdown actuation system reliability
|
Shukla, Darpan Krishnakumar
|
|
|
157 |
C |
p.
|
article
|
| 8 |
A nodal transport method for coupled fast-thermal reactor analysis
|
Deng, Puran
|
|
|
157 |
C |
p.
|
article
|
| 9 |
A quasi-3D direct transport method in the direct transport code KuaFu
|
Zhao, Chen
|
|
|
157 |
C |
p.
|
article
|
| 10 |
A review of uncertainties in the assessment of the radiological impact of liquid releases to the Ignalina NPP cooling pond lake Drūkšiai
|
Ragaišis, Valdas
|
|
|
157 |
C |
p.
|
article
|
| 11 |
Artificial Neural Network based Particle Swarm Optimization solution approach for the inverse depletion of used nuclear fuel
|
Khuwaileh, Bassam A.
|
|
|
157 |
C |
p.
|
article
|
| 12 |
Benchmark on neutron flux spatial effects in subcritical system based on IRT-4 M fuel for near-core positions
|
Bily, Tomas
|
|
|
157 |
C |
p.
|
article
|
| 13 |
Comparative studies of iterative methods for solving the “optimally diffusive” coarse mesh finite difference accelerated transport equation
|
Jain, Lakshay
|
|
|
157 |
C |
p.
|
article
|
| 14 |
Comparison of occupational exposure according to dismantling strategy of Kori nuclear power plant unit #1 bio-shield
|
Lee, ChoongWie
|
|
|
157 |
C |
p.
|
article
|
| 15 |
Current state of partitioning and transmutation studies for advanced nuclear fuel cycles
|
Kooyman, T.
|
|
|
157 |
C |
p.
|
article
|
| 16 |
Editorial Board
|
|
|
|
157 |
C |
p.
|
article
|
| 17 |
Effects of M2O3 (M = Bi, Al) on silver vanadate glass for radioactive iodine immobilization
|
Kang, Hyun Woo
|
|
|
157 |
C |
p.
|
article
|
| 18 |
Erratum to “Non-intrusive stochastic approach for nuclear cross-sections adjustment” [Ann. Nucl. Energy 155 (2021) 108162]
|
Huang, Dongli
|
|
|
157 |
C |
p.
|
article
|
| 19 |
Integral experiments in the VENUS-F reactor
|
Kochetkov, A.
|
|
|
157 |
C |
p.
|
article
|
| 20 |
Investigating fission distribution behavior under various homogenization techniques for asymmetrical fuel assemblies and different reflector equivalence methods
|
Fröhlicher, Kévin
|
|
|
157 |
C |
p.
|
article
|
| 21 |
Massimo Salvatores’ seminal ideas and comprehensive views on nuclear fuel cycle studies
|
Fazio, Concetta
|
|
|
157 |
C |
p.
|
article
|
| 22 |
Numerical analysis of the equalization capability of submerged perforated sheets for wwer-1500 horizontal steam generator
|
Le, T.T.
|
|
|
157 |
C |
p.
|
article
|
| 23 |
Numerical comparison of mathematical and computational models for the simulation of stochastic neutron kinetics problems
|
Gordon, T.L.
|
|
|
157 |
C |
p.
|
article
|
| 24 |
Optimization of forced circulation to natural circulation transition characteristics of IPWR
|
Xu, Yifan
|
|
|
157 |
C |
p.
|
article
|
| 25 |
Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor
|
Zhou, Lei
|
|
|
157 |
C |
p.
|
article
|
| 26 |
Review of the tube external condensation heat transfer characteristic of the passive containment cooling system in nuclear power plant
|
Chen, Weixiong
|
|
|
157 |
C |
p.
|
article
|
| 27 |
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
|
Verma, V.
|
|
|
157 |
C |
p.
|
article
|
| 28 |
Theoretical research on two-phase flow instability in parallel channels under periodic heaving motion condition
|
Qian, Libo
|
|
|
157 |
C |
p.
|
article
|
| 29 |
Thermal-hydraulic performance of a PCHE with sodium and sCO2 as working fluids
|
Cong, Tenglong
|
|
|
157 |
C |
p.
|
article
|
| 30 |
Thermal neutron scattering measurements and modeling of yttrium-hydrides for high temperature moderator applications
|
Chapman, Chris W.
|
|
|
157 |
C |
p.
|
article
|
Journal description