| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Adaptive robust control for axial offset in the P.W.R nuclear reactors based on the multipoint reactor model during load-following operation
|
Zaidabadi nejad, M.
|
|
2017
|
103 |
C |
p. 251-264
|
artikel
|
| 2 |
A kaolinite-based filter to capture gaseous cesium compounds in off-gas released during the pyroprocessing head-end process
|
Yang, Jae Hwan
|
|
2017
|
103 |
C |
p. 29-35
|
artikel
|
| 3 |
A methodology to simulate the cutting process for a nuclear dismantling simulation based on a digital manufacturing platform
|
Hyun, Dongjun
|
|
2017
|
103 |
C |
p. 369-383
|
artikel
|
| 4 |
Analysis of the equalizing holes resistance in fuel assembly spike for lead-based reactor
|
Zhang, Guangyu
|
|
2017
|
103 |
C |
p. 10-16
|
artikel
|
| 5 |
An enhanced search algorithm for the charged fuel enrichment in equilibrium cycle analysis of REBUS-3
|
Park, Tongkyu
|
|
2017
|
103 |
C |
p. 17-28
|
artikel
|
| 6 |
A novel approach for fault detection and classification of the thermocouple sensor in Nuclear Power Plant using Singular Value Decomposition and Symbolic Dynamic Filter
|
Mandal, Shyamapada
|
|
2017
|
103 |
C |
p. 440-453
|
artikel
|
| 7 |
A PLC platform-independent structural analysis on FBD programs for digital reactor protection systems
|
Jung, Sejin
|
|
2017
|
103 |
C |
p. 454-469
|
artikel
|
| 8 |
Application of process monitoring to anomaly detection in nuclear material processing systems via system-centric event interpretation of data from multiple sensors of varying reliability
|
Garcia, Humberto E.
|
|
2017
|
103 |
C |
p. 60-73
|
artikel
|
| 9 |
Application of the Karhunen–Loève Transform to the C5G7 benchmark in the response matrix method
|
Reed, Richard L.
|
|
2017
|
103 |
C |
p. 350-355
|
artikel
|
| 10 |
Assessment of an X-ray analysis system for investigating of fibrous debris bed formation on PWR sump strainer modules
|
LaBrier, Daniel
|
|
2017
|
103 |
C |
p. 393-401
|
artikel
|
| 11 |
Benchmarking of nuclear economics tools
|
Moore, Megan
|
|
2017
|
103 |
C |
p. 122-129
|
artikel
|
| 12 |
Burnup optimization of Small Natural Circulation Lead Cooled Fast Reactor
|
Zhang, Haoran
|
|
2017
|
103 |
C |
p. 424-430
|
artikel
|
| 13 |
CFD thermo-hydraulic analysis of the CIRCE fuel bundle
|
Martelli, Daniele
|
|
2017
|
103 |
C |
p. 294-305
|
artikel
|
| 14 |
Code-to-code comparisons of lattice physics calculations for thorium-augmented and thorium-based fuels in pressure tube heavy water reactors
|
Colton, A.
|
|
2017
|
103 |
C |
p. 194-203
|
artikel
|
| 15 |
Continuous spectrum of linear transport equation for different boundary conditions
|
Sahni, D.C.
|
|
2017
|
103 |
C |
p. 157-162
|
artikel
|
| 16 |
Design of emergency shutdown system for the Tehran Research Reactor; Part I: Neutronics investigation
|
Safarinia, M.
|
|
2017
|
103 |
C |
p. 306-314
|
artikel
|
| 17 |
Development of an Application Programming Interface for Depletion Analysis (APIDA)
|
Lago, Daniel
|
|
2017
|
103 |
C |
p. 163-172
|
artikel
|
| 18 |
Editorial board
|
|
|
2017
|
103 |
C |
p. IFC
|
artikel
|
| 19 |
Effects of oxidation states of fuel cladding surface on crud deposition in simulated primary water of PWRs
|
Park, Moon-Sic
|
|
2017
|
103 |
C |
p. 275-281
|
artikel
|
| 20 |
Experimental and numerical study on single-phase flow characteristics of natural circulation system with heated narrow rectangular channel under rolling motion condition
|
Yu, Shengzhi
|
|
2017
|
103 |
C |
p. 97-113
|
artikel
|
| 21 |
Experiments in LEENA facility with modified wire type leak detector layout in large sodium pipelines
|
Vijayakumar, G.
|
|
2017
|
103 |
C |
p. 326-333
|
artikel
|
| 22 |
Feature extraction and sensor selection for NPP initiating event identification
|
Lin, Ting-Han
|
|
2017
|
103 |
C |
p. 384-392
|
artikel
|
| 23 |
Identification model of an accidental drop of a control rod in PWR reactors using thermocouple readings and radial basis function neural networks
|
Souza, T.J.
|
|
2017
|
103 |
C |
p. 204-211
|
artikel
|
| 24 |
Image-processing of time-averaged interface distributions representing CCFL characteristics in a large scale model of a PWR hot-leg pipe geometry
|
Al Issa, Suleiman
|
|
2017
|
103 |
C |
p. 282-293
|
artikel
|
| 25 |
Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors
|
Toti, A.
|
|
2017
|
103 |
C |
p. 36-48
|
artikel
|
| 26 |
Investigation of CO2 leak accident in SFR coupled with S-CO2 Brayton cycle
|
Jung, Hwa-Young
|
|
2017
|
103 |
C |
p. 212-226
|
artikel
|
| 27 |
Investigation on the potential use of thorium as fuel for the Sodium-cooled Fast Reactor
|
György, H.
|
|
2017
|
103 |
C |
p. 238-250
|
artikel
|
| 28 |
MAAP 5.04 ex-vessel CRD tube heat transfer and melting model
|
Lim, Jaehyok
|
|
2017
|
103 |
C |
p. 265-274
|
artikel
|
| 29 |
Mathematical spacer grid models for single phase flow
|
Maskal, Alan B.
|
|
2017
|
103 |
C |
p. 130-146
|
artikel
|
| 30 |
Mathematical spacer grid models for two phase flow
|
Maskal, Alan B.
|
|
2017
|
103 |
C |
p. 173-193
|
artikel
|
| 31 |
Measurement of reactivity in a source driven deep sub-critical system using neutron noise methods
|
Kumar, Rajeev
|
|
2017
|
103 |
C |
p. 315-325
|
artikel
|
| 32 |
Measurement, simulation, and meteorological interpretation of medium-range transport of radionuclides to Korea during the Fukushima Dai-ichi nuclear accident
|
Lee, Hyo-Jung
|
|
2017
|
103 |
C |
p. 412-423
|
artikel
|
| 33 |
Numerical investigation of the random arrangement effect of coated fuel particles on the criticality of HTTR fuel compact using MCNP6
|
Ho, Hai Quan
|
|
2017
|
103 |
C |
p. 114-121
|
artikel
|
| 34 |
Numerical simulation of MCCI based on MPS method with different types of concrete
|
Chai, Penghui
|
|
2017
|
103 |
C |
p. 227-237
|
artikel
|
| 35 |
Performance analysis of heat pipe radiator unit for space nuclear power reactor
|
Wang, Chenglong
|
|
2017
|
103 |
C |
p. 74-84
|
artikel
|
| 36 |
Performance and accuracy of criticality calculations performed using WARP – A framework for continuous energy Monte Carlo neutron transport in general 3D geometries on GPUs
|
Bergmann, Ryan M.
|
|
2017
|
103 |
C |
p. 334-349
|
artikel
|
| 37 |
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis
|
Brown, Nicholas R.
|
|
2017
|
103 |
C |
p. 49-59
|
artikel
|
| 38 |
Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient
|
Wu, Guowei
|
|
2017
|
103 |
C |
p. 1-9
|
artikel
|
| 39 |
Removal of strontium ions from simulated radioactive wastewater by vacuum membrane distillation
|
Jia, Fei
|
|
2017
|
103 |
C |
p. 363-368
|
artikel
|
| 40 |
Stochastic processes during transients in nuclear reactors
|
Difilippo, Felix C.
|
|
2017
|
103 |
C |
p. 431-439
|
artikel
|
| 41 |
Symbiotic equilibrium between Sodium Fast Reactors and Pressurized Water Reactors supplied with MOX fuel
|
Martin, G.
|
|
2017
|
103 |
C |
p. 356-362
|
artikel
|
| 42 |
Testing the new stochastic neutronic code ANET in simulating safety important parameters
|
Xenofontos, T.
|
|
2017
|
103 |
C |
p. 85-96
|
artikel
|
| 43 |
The evaluation of different trial shape functions applied in Spectral Element Method in analysis of multi-group Pn transport equation
|
Nahavandi, N.
|
|
2017
|
103 |
C |
p. 147-156
|
artikel
|
| 44 |
Theory of Feynman-alpha technique with masking window for accelerator-driven systems
|
Kitamura, Yasunori
|
|
2017
|
103 |
C |
p. 470-479
|
artikel
|
| 45 |
The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant
|
Wang, Te-Chuan
|
|
2017
|
103 |
C |
p. 402-411
|
artikel
|
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