| no |
title |
author |
magazine |
year |
volume |
issue |
page(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
|
article
|
| 2 |
A fully-implicit high-order system thermal-hydraulics model for advanced non-LWR safety analyses
|
Hu, Rui
|
|
2017
|
101 |
C |
p. 174-181
|
article
|
| 3 |
Analysis and solution of current spike occurred in dynamic compensation of self-powered neutron detectors
|
Peng, Xingjie
|
|
2017
|
101 |
C |
p. 83-88
|
article
|
| 4 |
Analysis of KUCA measurements by the reactivity monitoring MAρTA method
|
Dulla, Sandra
|
|
2017
|
101 |
C |
p. 397-407
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 8 |
Applied research of Primary Pump Mission Profile construction
|
Zheng, Gang-yang
|
|
2017
|
101 |
C |
p. 528-533
|
article
|
| 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
|
article
|
| 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
|
article
|
| 11 |
BEAVRS full core burnup calculation in hot full power condition by RMC code
|
Liu, Shichang
|
|
2017
|
101 |
C |
p. 434-446
|
article
|
| 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
|
article
|
| 13 |
Cofrentes nuclear power plant instability analysis using ensemble empirical mode decomposition (EEMD)
|
Montalvo, C.
|
|
2017
|
101 |
C |
p. 390-396
|
article
|
| 14 |
Comparisons of SN and Monte-Carlo methods in PWR ex-core detector response simulation
|
Zheng, Youqi
|
|
2017
|
101 |
C |
p. 139-150
|
article
|
| 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
|
article
|
| 16 |
Coupled simulations of the NACIE facility using RELAP5 and ANSYS FLUENT codes
|
Martelli, Daniele
|
|
2017
|
101 |
C |
p. 408-418
|
article
|
| 17 |
1-D dynamic stability analysis of mixed-spectrum supercritical water reactor core
|
Liu, Pengfei
|
|
2017
|
101 |
C |
p. 278-292
|
article
|
| 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
|
article
|
| 19 |
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
|
Hursin, M.
|
|
2017
|
101 |
C |
p. 559-575
|
article
|
| 20 |
Development of a transverse mixing model for large scale impulsion phenomenon in tight lattice
|
Liu, Xiaojing
|
|
2017
|
101 |
C |
p. 159-165
|
article
|
| 21 |
Development of fuel temperature calculation code for HTGRs
|
Inaba, Yoshitomo
|
|
2017
|
101 |
C |
p. 383-389
|
article
|
| 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
|
article
|
| 23 |
Editorial board
|
|
|
2017
|
101 |
C |
p. IFC
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 27 |
Evaluation of hydraulic characteristics of core flow monitoring mechanism for PFBR
|
Shivakumar, N.S.
|
|
2017
|
101 |
C |
p. 322-329
|
article
|
| 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
|
article
|
| 29 |
Experiments on silver-indium-cadmium control rod failure during severe nuclear accidents
|
Steinbrück, M.
|
|
2017
|
101 |
C |
p. 347-358
|
article
|
| 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
|
article
|
| 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
|
article
|
| 32 |
Hybrid nuclear plant simulator design requirements to enable dynamic diagnostics of plant operations
|
Ayo-Imoru, R.M.
|
|
2017
|
101 |
C |
p. 447-453
|
article
|
| 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
|
article
|
| 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
|
article
|
| 35 |
Investigation on generalized Variational Nodal Methods for heterogeneous nodes
|
Wang, Yongping
|
|
2017
|
101 |
C |
p. 36-48
|
article
|
| 36 |
Isogeometric analysis for the multigroup neutron diffusion equation with applications in reactor physics
|
Welch, J.A.
|
|
2017
|
101 |
C |
p. 465-480
|
article
|
| 37 |
Leaching performance of uranium from the cement solidified matrices containing spent radioactive organic solvent
|
Zhang, Wenfeng
|
|
2017
|
101 |
C |
p. 31-35
|
article
|
| 38 |
Mechanical and radiation shielding properties of mortars with additive fine aggregate mine waste
|
Gallala, Wissem
|
|
2017
|
101 |
C |
p. 600-606
|
article
|
| 39 |
Modeling and verification of three-dimensional simulation for BWR in-vessel core degradation
|
Okawa, Tsuyoshi
|
|
2017
|
101 |
C |
p. 182-195
|
article
|
| 40 |
Modeling of flashing-induced flow instabilities for a natural circulation driven novel modular reactor
|
Shi, Shanbin
|
|
2017
|
101 |
C |
p. 215-225
|
article
|
| 41 |
Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
|
Betzler, Benjamin R.
|
|
2017
|
101 |
C |
p. 489-503
|
article
|
| 42 |
Natural circulation thermal-hydraulics model and analyses of “SLIMM” – A small modular reactor
|
Haskins, Denise A.
|
|
2017
|
101 |
C |
p. 516-527
|
article
|
| 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
|
article
|
| 44 |
Nuclear data uncertainty propagation to integral responses using SANDY
|
Fiorito, L.
|
|
2017
|
101 |
C |
p. 359-366
|
article
|
| 45 |
Numerical investigation on the thermal stratification in a pressurizer surge line
|
Cai, Benan
|
|
2017
|
101 |
C |
p. 293-300
|
article
|
| 46 |
Numerical study on non-axisymmetric wall thinning in pipelines with swirling flow
|
Yamagata, Takayuki
|
|
2017
|
101 |
C |
p. 196-202
|
article
|
| 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
|
article
|
| 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
|
article
|
| 49 |
Pressure losses and interfacial drag for two-phase flow in porous beds with coarse particles
|
Li, Liangxing
|
|
2017
|
101 |
C |
p. 481-488
|
article
|
| 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
|
article
|
| 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
|
article
|
| 52 |
Screening the design space for optimized plutonium incineration performance in the thorium-based I2S-LWR
|
Kotlyar, D.
|
|
2017
|
101 |
C |
p. 237-249
|
article
|
| 53 |
SFR mechanical scenarios and neutron transport transients with CAST3M code
|
Kępisty, Grzegorz
|
|
2017
|
101 |
C |
p. 226-236
|
article
|
| 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
|
article
|
| 55 |
The homogeneous and Lagrangian tracking approaches of the spray simulation in the containment
|
Ding, Peng
|
|
2017
|
101 |
C |
p. 203-214
|
article
|
| 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
|
article
|
| 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
|
article
|
| 58 |
The use of representativity theory in the depletion calculations of SFR blankets
|
Lebrat, Jean-François
|
|
2017
|
101 |
C |
p. 429-433
|
article
|
| 59 |
Towards proliferation-resistant thorium fuels
|
Alhaj, M. Yousif
|
|
2017
|
101 |
C |
p. 586-590
|
article
|
| 60 |
Transient flow analysis of the single cylinder for the control rod hydraulic driving system
|
Sun, Xinming
|
|
2017
|
101 |
C |
p. 151-158
|
article
|
| 61 |
Transient performance of a dual disc check valve during the opening period
|
Lai, Zhounian
|
|
2017
|
101 |
C |
p. 15-22
|
article
|
| 62 |
Uncertainty analysis of minor actinides transmutation in fast reactor cores
|
Takeda, Toshikazu
|
|
2017
|
101 |
C |
p. 591-599
|
article
|
Journal description