| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparison of failure assessment diagram options for Inconel 690 and Incoloy 800 nuclear steam generators tubes
|
Bergant, Marcos A.
|
|
|
140 |
C |
p.
|
artikel
|
| 2 |
Advanced method for neutronics and system code coupling RELAP, PARCS, and MATLAB for instrumentation and control assessment
|
Busquim e Silva, R.A.
|
|
|
140 |
C |
p.
|
artikel
|
| 3 |
A functional variable universe fuzzy PID controller for load following operation of PWR with the multiple model
|
Zeng, Wenjie
|
|
|
140 |
C |
p.
|
artikel
|
| 4 |
A hybrid continuous energy and multi-group Monte Carlo method
|
Kowalski, Mikolaj Adam
|
|
|
140 |
C |
p.
|
artikel
|
| 5 |
A mixed intelligent condition monitoring method for nuclear power plant
|
Peng, Binsen
|
|
|
140 |
C |
p.
|
artikel
|
| 6 |
A new method for the localisation of gas leaker fuel subassemblies in fast breeder reactors
|
Sarangapani, R.
|
|
|
140 |
C |
p.
|
artikel
|
| 7 |
A parallel DSA algorithm in the 3-D cylindrical geometry
|
Xu, Longfei
|
|
|
140 |
C |
p.
|
artikel
|
| 8 |
A reference neutron field for measurement of spectrum averaged cross sections
|
Košťál, Michal
|
|
|
140 |
C |
p.
|
artikel
|
| 9 |
Calculation of multi-group migration areas in deterministic transport simulations
|
Liu, Zhaoyuan
|
|
|
140 |
C |
p.
|
artikel
|
| 10 |
CFD study on mechanisms of fission gas burst release from defective fuel rods of a typical PWR
|
Dong, Bing
|
|
|
140 |
C |
p.
|
artikel
|
| 11 |
Combined cycles-coupled high-temperature and very high-temperature gas-cooled reactors: Part II – Engineering design
|
Qu, Xinhe
|
|
|
140 |
C |
p.
|
artikel
|
| 12 |
Comments on the paper: Xingjie Peng et al. 2018. “Reactor core power mapping based on Bayesian inference”, Ann. Nucl. Energy 119, 322–330
|
Hoefer, Axel
|
|
|
140 |
C |
p.
|
artikel
|
| 13 |
Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT
|
Woolstenhulme, Nicolas
|
|
|
140 |
C |
p.
|
artikel
|
| 14 |
Corrigendum to papers: 1. A theory of low source startup based on the Pal-Bell equations [Ann Nucl Energy 102 (2017) 317]. 2. Spatial effects in low neutron source startup and associated stochastic phenomena [Ann Nucl Energy 111 (2018) 616]
|
Williams, M.M.R.
|
|
|
140 |
C |
p.
|
artikel
|
| 15 |
Detection of fuel failure in pressurized water reactor with artificial neural network
|
Dong, Bing
|
|
|
140 |
C |
p.
|
artikel
|
| 16 |
Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage
|
Gao, Yuan
|
|
|
140 |
C |
p.
|
artikel
|
| 17 |
3D simulation model of water infiltration for radioactive waste on a virtual reality Environment: An application to the Abadia de Goiás repository
|
Gabcan, L.
|
|
|
140 |
C |
p.
|
artikel
|
| 18 |
Dynamic reliability analysis framework for passive safety systems of Nuclear Power Plant
|
Tripathi, A. Manish
|
|
|
140 |
C |
p.
|
artikel
|
| 19 |
Editorial Board
|
|
|
|
140 |
C |
p.
|
artikel
|
| 20 |
Effect of physical property parameters on critical airflow velocity of a corrugated plate dryer
|
Wang, Bo
|
|
|
140 |
C |
p.
|
artikel
|
| 21 |
Effect on hydrogen risk of total amount of inert gas during post-inerting in AP1000 NPP
|
Lyu, Xuefeng
|
|
|
140 |
C |
p.
|
artikel
|
| 22 |
Experimental measurements of flow mixing in cold leg of a pressurized water reactor
|
Orea, Daniel
|
|
|
140 |
C |
p.
|
artikel
|
| 23 |
Experimental research on the fragmentation of continuous molten 316SS droplets penetrating into sodium pool
|
Yang, Zhi
|
|
|
140 |
C |
p.
|
artikel
|
| 24 |
Experimental study of transient friction characteristics and velocity distribution of pulsatile flow in rod bundles
|
Li, Xing
|
|
|
140 |
C |
p.
|
artikel
|
| 25 |
Experimental visualization of flow structure inside subchannels of a 4 × 6 rod-bundle
|
Kim, Seok
|
|
|
140 |
C |
p.
|
artikel
|
| 26 |
Extension and application of the KIKO3DMG nodal code for fast reactor core analyses
|
Batki, Bálint
|
|
|
140 |
C |
p.
|
artikel
|
| 27 |
Extension of the subgroup method for self-shielding calculation of fully ceramic micro-encapsulated fuel
|
He, Qingming
|
|
|
140 |
C |
p.
|
artikel
|
| 28 |
Fracture characterization studies of concrete structures through experiments on reinforced concrete cylindrical shell specimens
|
Trivedi, Neha
|
|
|
140 |
C |
p.
|
artikel
|
| 29 |
Friction and local pressure loss characteristics of a 5 × 5 rod bundle with spacer grids
|
Ma, Zaiyong
|
|
|
140 |
C |
p.
|
artikel
|
| 30 |
Highly efficient elimination of uranium from wastewater with facilely synthesized Mg-Fe layered double hydroxides: Optimum preparation conditions and adsorption kinetics
|
Li, Peng
|
|
|
140 |
C |
p.
|
artikel
|
| 31 |
Interpretation of the ASPIS Iron 88 programme with TRIPOLI-4® and quantification of uncertainties due to nuclear data
|
Hajji, Amine
|
|
|
140 |
C |
p.
|
artikel
|
| 32 |
Investigation on the depletion calculation with neutronic-temperature coupling in the fuel pellet of light water reactor
|
Zhang, Qian
|
|
|
140 |
C |
p.
|
artikel
|
| 33 |
Measurement of the U-238/U-235 fission cross section ratio at CSNS – Back-n WNS
|
Wen, Jie
|
|
|
140 |
C |
p.
|
artikel
|
| 34 |
Methodology for a realistically conservative characterization of spent fuel in dry storage
|
Feria, F.
|
|
|
140 |
C |
p.
|
artikel
|
| 35 |
Modified least-squares finite element method for solving the Boltzmann transport equation with spherical harmonic angular approximation
|
Fang, Chao
|
|
|
140 |
C |
p.
|
artikel
|
| 36 |
Molten salt reactor core simulation with PROTEUS
|
Fei, T.
|
|
|
140 |
C |
p.
|
artikel
|
| 37 |
Monte Carlo sensitivity analysis method for the effective delayed neutron fraction with the differential operator sampling method
|
Yamamoto, Toshihiro
|
|
|
140 |
C |
p.
|
artikel
|
| 38 |
Multi-group lattice Boltzmann method for criticality problems
|
Agarwal, Gaurav
|
|
|
140 |
C |
p.
|
artikel
|
| 39 |
Neutronic investigation of the thorium-based mixed-oxide as an alternative fuel in the TRIGA Mark-II research reactor – Part I: A beginning of life calculations
|
Kabach, Ouadie
|
|
|
140 |
C |
p.
|
artikel
|
| 40 |
Nuclear-data uncertainty propagation in transient simulation for the C5G7-TD benchmark problem
|
Wan, Chenghui
|
|
|
140 |
C |
p.
|
artikel
|
| 41 |
Numerical investigation on the effects of geometric deviations and materials properties on flow-induced deflections of fuel plates
|
González Mantecón, Javier
|
|
|
140 |
C |
p.
|
artikel
|
| 42 |
Numerical investigation on the interactions of flow induced vibrations among neighboring cylinders in a cylinder bundle
|
Tang, Di
|
|
|
140 |
C |
p.
|
artikel
|
| 43 |
Numerical scaling assessment on natural circulation in Core Makeup Tank
|
Li, Xiangbin
|
|
|
140 |
C |
p.
|
artikel
|
| 44 |
Numerical simulation study on the flow and heat transfer characteristics of sub-cooled boiling in vertical round and flattened tubes
|
Tao, Han-zhong
|
|
|
140 |
C |
p.
|
artikel
|
| 45 |
Numerical solution of two-energy-group neutron noise diffusion problems with fine spatial meshes
|
Mylonakis, Antonios G.
|
|
|
140 |
C |
p.
|
artikel
|
| 46 |
On the relevance of turbulent structures resolution for cross-flow in a helical-coil tube bundle
|
Feng, Jinyong
|
|
|
140 |
C |
p.
|
artikel
|
| 47 |
Optimization design for supercritical carbon dioxide compressor based on simulated annealing algorithm
|
Tang, Songsheng
|
|
|
140 |
C |
p.
|
artikel
|
| 48 |
PIV measurement and CFD analysis of the turbulent flow in a 3 × 3 rod bundle
|
Wang, Han
|
|
|
140 |
C |
p.
|
artikel
|
| 49 |
Problem-dependent compression method for burnup library
|
Zhang, Yunfei
|
|
|
140 |
C |
p.
|
artikel
|
| 50 |
Response to: Comments on the paper Xingjie Peng et al. 2018. “Reactor core power mapping based on Bayesian inference” [Ann. Nucl. Energy 119, 322–330]
|
Peng, Xingjie
|
|
|
140 |
C |
p.
|
artikel
|
| 51 |
Review of the potential sources of organic iodides in a NPP containment during a severe accident and remaining uncertainties
|
Bosland, L.
|
|
|
140 |
C |
p.
|
artikel
|
| 52 |
SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems
|
Bostelmann, Friederike
|
|
|
140 |
C |
p.
|
artikel
|
| 53 |
Secure embedded intelligence in nuclear systems: Framework and methods
|
Garcia, Humberto E.
|
|
|
140 |
C |
p.
|
artikel
|
| 54 |
Stochastic-deterministic response matrix method for reactor transients
|
Mickus, Ignas
|
|
|
140 |
C |
p.
|
artikel
|
| 55 |
Superhistory-based differential operator method for generalized responses sensitivity calculations
|
Shi, Guanlin
|
|
|
140 |
C |
p.
|
artikel
|
| 56 |
The potentiality of thermal safety and economy of the U3Si2-SiC system in PWR
|
He, Sihong
|
|
|
140 |
C |
p.
|
artikel
|
| 57 |
Transmutation of radioactive cesium and iodine using gamma-radiation from light nuclei under proton bombardment
|
Zhu, Zhi-chao
|
|
|
140 |
C |
p.
|
artikel
|
| 58 |
Uncertainty quantification of proper orthogonal decomposition based online power-distribution reconstruction
|
Li, Zhuo
|
|
|
140 |
C |
p.
|
artikel
|
| 59 |
Variable coefficient depletion equations – Efficient calculation method
|
Huang, Kai
|
|
|
140 |
C |
p.
|
artikel
|
| 60 |
Verification of the 3D capability of OpenMOC with the C5G7 3D extension benchmark
|
Wu, Wenbin
|
|
|
140 |
C |
p.
|
artikel
|
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