nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A comparison of fission product behavior for typical PLWR and PHWR with FCVS operation
|
Park, S.Y. |
|
2017 |
101 |
C |
p. 99-108 |
artikel |
2 |
A fully-implicit high-order system thermal-hydraulics model for advanced non-LWR safety analyses
|
Hu, Rui |
|
2017 |
101 |
C |
p. 174-181 |
artikel |
3 |
Analysis and solution of current spike occurred in dynamic compensation of self-powered neutron detectors
|
Peng, Xingjie |
|
2017 |
101 |
C |
p. 83-88 |
artikel |
4 |
Analysis of KUCA measurements by the reactivity monitoring MAρTA method
|
Dulla, Sandra |
|
2017 |
101 |
C |
p. 397-407 |
artikel |
5 |
Analysis of multi-scale spatial separation in a block-type thorium-loaded helium-cooled high-temperature reactor
|
Huang, Jie |
|
2017 |
101 |
C |
p. 89-98 |
artikel |
6 |
An experimental investigation on relationship between PSFs and operator performances in the digital main control room
|
Park, Jooyoung |
|
2017 |
101 |
C |
p. 58-68 |
artikel |
7 |
A numerical simulation of thermo-mechanical behavior of the intact rock in response to the Borehole Heater Test
|
Ali, Syed Danial |
|
2017 |
101 |
C |
p. 301-311 |
artikel |
8 |
Applied research of Primary Pump Mission Profile construction
|
Zheng, Gang-yang |
|
2017 |
101 |
C |
p. 528-533 |
artikel |
9 |
Assessment of performing experimental investigation on a pebble bed modular reactor (PBMR) as a static packed bed approximation
|
Khane, Vaibhav |
|
2017 |
101 |
C |
p. 339-346 |
artikel |
10 |
A three-dimensional nodal neutron kinetics code with a higher-accuracy algorithm for reactor core in hexagonal-z geometry
|
Lu, Daogang |
|
2017 |
101 |
C |
p. 250-261 |
artikel |
11 |
BEAVRS full core burnup calculation in hot full power condition by RMC code
|
Liu, Shichang |
|
2017 |
101 |
C |
p. 434-446 |
artikel |
12 |
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
|
Aures, A. |
|
2017 |
101 |
C |
p. 262-269 |
artikel |
13 |
Cofrentes nuclear power plant instability analysis using ensemble empirical mode decomposition (EEMD)
|
Montalvo, C. |
|
2017 |
101 |
C |
p. 390-396 |
artikel |
14 |
Comparisons of SN and Monte-Carlo methods in PWR ex-core detector response simulation
|
Zheng, Youqi |
|
2017 |
101 |
C |
p. 139-150 |
artikel |
15 |
Consistent adjustment of radioactive decay and fission yields data with measurement data of decay heat and β -delayed neutron activities
|
Chiba, Go |
|
2017 |
101 |
C |
p. 23-30 |
artikel |
16 |
Coupled simulations of the NACIE facility using RELAP5 and ANSYS FLUENT codes
|
Martelli, Daniele |
|
2017 |
101 |
C |
p. 408-418 |
artikel |
17 |
1-D dynamic stability analysis of mixed-spectrum supercritical water reactor core
|
Liu, Pengfei |
|
2017 |
101 |
C |
p. 278-292 |
artikel |
18 |
Demonstration of an improved passive acoustic fault detection method on recordings from the Phénix steam generator operating at full power
|
Riber Marklund, Anders |
|
2017 |
101 |
C |
p. 1-14 |
artikel |
19 |
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
|
Hursin, M. |
|
2017 |
101 |
C |
p. 559-575 |
artikel |
20 |
Development of a transverse mixing model for large scale impulsion phenomenon in tight lattice
|
Liu, Xiaojing |
|
2017 |
101 |
C |
p. 159-165 |
artikel |
21 |
Development of fuel temperature calculation code for HTGRs
|
Inaba, Yoshitomo |
|
2017 |
101 |
C |
p. 383-389 |
artikel |
22 |
Development of siphon breaker simulation program for investing loss of coolant accident of a research reactor
|
Lee, Kwon-Yeong |
|
2017 |
101 |
C |
p. 49-57 |
artikel |
23 |
Editorial board
|
|
|
2017 |
101 |
C |
p. IFC |
artikel |
24 |
Enhancements to the Nodal Drift Method for a Rod Ejection Accident in a PWR-like mini-core with lumped thermal model
|
Prévot, P. |
|
2017 |
101 |
C |
p. 128-138 |
artikel |
25 |
ENTRANS: A platform for finite elements modeling of 3D neutron transport equation, Part II. Multidimensional implementation
|
Yousefi, Mostafa |
|
2017 |
101 |
C |
p. 534-551 |
artikel |
26 |
Evaluation and optimization of thermoelectric generator network for waste heat utilization in nuclear power plants and non-nuclear energy applications
|
Gabbar, Hossam A. |
|
2017 |
101 |
C |
p. 454-464 |
artikel |
27 |
Evaluation of hydraulic characteristics of core flow monitoring mechanism for PFBR
|
Shivakumar, N.S. |
|
2017 |
101 |
C |
p. 322-329 |
artikel |
28 |
Experimental study on cryogenic adsorption of methane by activated carbon for helium coolant purification of High-Temperature Gas-cooled Reactor
|
Chang, Hua |
|
2017 |
101 |
C |
p. 367-374 |
artikel |
29 |
Experiments on silver-indium-cadmium control rod failure during severe nuclear accidents
|
Steinbrück, M. |
|
2017 |
101 |
C |
p. 347-358 |
artikel |
30 |
Extended Kalman filter design to estimate the poisons concentrations in the P.W.R nuclear reactors based on the reactor power measurement
|
Zahedi Ygane, M.H. |
|
2017 |
101 |
C |
p. 576-585 |
artikel |
31 |
Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor
|
Fiorina, Carlo |
|
2017 |
101 |
C |
p. 419-428 |
artikel |
32 |
Hybrid nuclear plant simulator design requirements to enable dynamic diagnostics of plant operations
|
Ayo-Imoru, R.M. |
|
2017 |
101 |
C |
p. 447-453 |
artikel |
33 |
Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium
|
Brown, Nicholas R. |
|
2017 |
101 |
C |
p. 166-173 |
artikel |
34 |
Implementation of the direct S ( α , β ) method in the KENO Monte Carlo code
|
Hart, Shane W.D. |
|
2017 |
101 |
C |
p. 270-277 |
artikel |
35 |
Investigation on generalized Variational Nodal Methods for heterogeneous nodes
|
Wang, Yongping |
|
2017 |
101 |
C |
p. 36-48 |
artikel |
36 |
Isogeometric analysis for the multigroup neutron diffusion equation with applications in reactor physics
|
Welch, J.A. |
|
2017 |
101 |
C |
p. 465-480 |
artikel |
37 |
Leaching performance of uranium from the cement solidified matrices containing spent radioactive organic solvent
|
Zhang, Wenfeng |
|
2017 |
101 |
C |
p. 31-35 |
artikel |
38 |
Mechanical and radiation shielding properties of mortars with additive fine aggregate mine waste
|
Gallala, Wissem |
|
2017 |
101 |
C |
p. 600-606 |
artikel |
39 |
Modeling and verification of three-dimensional simulation for BWR in-vessel core degradation
|
Okawa, Tsuyoshi |
|
2017 |
101 |
C |
p. 182-195 |
artikel |
40 |
Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor
|
Shi, Shanbin |
|
2017 |
101 |
C |
p. 215-225 |
artikel |
41 |
Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
|
Betzler, Benjamin R. |
|
2017 |
101 |
C |
p. 489-503 |
artikel |
42 |
Natural circulation thermal-hydraulics model and analyses of “SLIMM” – A small modular reactor
|
Haskins, Denise A. |
|
2017 |
101 |
C |
p. 516-527 |
artikel |
43 |
Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations
|
Romojaro, P. |
|
2017 |
101 |
C |
p. 330-338 |
artikel |
44 |
Nuclear data uncertainty propagation to integral responses using SANDY
|
Fiorito, L. |
|
2017 |
101 |
C |
p. 359-366 |
artikel |
45 |
Numerical investigation on the thermal stratification in a pressurizer surge line
|
Cai, Benan |
|
2017 |
101 |
C |
p. 293-300 |
artikel |
46 |
Numerical study on non-axisymmetric wall thinning in pipelines with swirling flow
|
Yamagata, Takayuki |
|
2017 |
101 |
C |
p. 196-202 |
artikel |
47 |
On multi-group neutron transport in planar one dimensional geometry: A solution for a localized pulsed source
|
Fernandes, J.C.L. |
|
2017 |
101 |
C |
p. 552-558 |
artikel |
48 |
Overview of the VERDON-ISTP Program and main insights from the VERDON-2 air ingress test
|
Gallais-During, A. |
|
2017 |
101 |
C |
p. 109-117 |
artikel |
49 |
Pressure losses and interfacial drag for two-phase flow in porous beds with coarse particles
|
Li, Liangxing |
|
2017 |
101 |
C |
p. 481-488 |
artikel |
50 |
Quantification of performance shaping factors (PSFs)’ weightings for human reliability analysis (HRA) of low power and shutdown (LPSD) operations
|
Kim, Ar Ryum |
|
2017 |
101 |
C |
p. 375-382 |
artikel |
51 |
RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor
|
Liu, Limin |
|
2017 |
101 |
C |
p. 504-515 |
artikel |
52 |
Screening the design space for optimized plutonium incineration performance in the thorium-based I2S-LWR
|
Kotlyar, D. |
|
2017 |
101 |
C |
p. 237-249 |
artikel |
53 |
SFR mechanical scenarios and neutron transport transients with CAST3M code
|
Kępisty, Grzegorz |
|
2017 |
101 |
C |
p. 226-236 |
artikel |
54 |
Study of the iodine kinetics in thermal conditions of a RCS in nuclear severe accident
|
Grégoire, A.-C. |
|
2017 |
101 |
C |
p. 69-82 |
artikel |
55 |
The homogeneous and Lagrangian tracking approaches of the spray simulation in the containment
|
Ding, Peng |
|
2017 |
101 |
C |
p. 203-214 |
artikel |
56 |
The neutronics scheme adopted for the HELIOS irradiation experiment in the High Flux Reactor Petten
|
D’Agata, E. |
|
2017 |
101 |
C |
p. 312-321 |
artikel |
57 |
Thermal hydraulic analysis of VVER-1000 nuclear reactor with dual-cooled annular fuel using K–ω SST Turbulence model
|
Zaidabadi, M. |
|
2017 |
101 |
C |
p. 118-127 |
artikel |
58 |
The use of representativity theory in the depletion calculations of SFR blankets
|
Lebrat, Jean-François |
|
2017 |
101 |
C |
p. 429-433 |
artikel |
59 |
Towards proliferation-resistant thorium fuels
|
Alhaj, M. Yousif |
|
2017 |
101 |
C |
p. 586-590 |
artikel |
60 |
Transient flow analysis of the single cylinder for the control rod hydraulic driving system
|
Sun, Xinming |
|
2017 |
101 |
C |
p. 151-158 |
artikel |
61 |
Transient performance of a dual disc check valve during the opening period
|
Lai, Zhounian |
|
2017 |
101 |
C |
p. 15-22 |
artikel |
62 |
Uncertainty analysis of minor actinides transmutation in fast reactor cores
|
Takeda, Toshikazu |
|
2017 |
101 |
C |
p. 591-599 |
artikel |