nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A comparative study on local fuel-coolant interactions in a liquid pool with different interaction modes
|
Cheng, Songbai |
|
2019 |
132 |
C |
p. 258-270 |
artikel |
2 |
A GPU-based direct Monte Carlo simulation of time dependence in nuclear reactors
|
Molnar, Balazs |
|
2019 |
132 |
C |
p. 46-63 |
artikel |
3 |
A hybrid acceleration method to pin-by-pin calculations using the heterogeneous variational nodal method
|
Zhang, Tengfei |
|
2019 |
132 |
C |
p. 723-733 |
artikel |
4 |
Analysis of the transient performance of the flashing-driven natural circulation IPWR
|
Zhao, Yanan |
|
2019 |
132 |
C |
p. 381-390 |
artikel |
5 |
A novel concept for a molten salt reactor moderated by heavy water
|
Wu, Jianhui |
|
2019 |
132 |
C |
p. 391-403 |
artikel |
6 |
A study of burnup credit in criticality safety analysis for PBR spent fuel pebbles
|
Wu, Shang-Chien |
|
2019 |
132 |
C |
p. 347-356 |
artikel |
7 |
A three-dimensional approach for simulating BWR core melt progression – A validation against CORA-BWR experimental series
|
Okawa, Tsuyoshi |
|
2019 |
132 |
C |
p. 512-525 |
artikel |
8 |
A unified space–time fully-transversed general nodal expansion method for multidimensional and multigroup steady and transient nuclear reactor neutronics problems
|
Zhou, Xiafeng |
|
2019 |
132 |
C |
p. 427-441 |
artikel |
9 |
Boron-10 effect on the reactivity of the IPR-R1 Triga research reactor
|
Mesquita, Amir Zacarias |
|
2019 |
132 |
C |
p. 64-69 |
artikel |
10 |
Comparative study of application of different supervised learning methods in forecasting future states of NPPs operating parameters
|
Moshkbar-Bakhshayesh, Khalil |
|
2019 |
132 |
C |
p. 87-99 |
artikel |
11 |
Comparison of analytical and numerical solutions for the multigroup diffusion theory analysis of circulating fuel reactors
|
Ozgener, H. Atilla |
|
2019 |
132 |
C |
p. 636-655 |
artikel |
12 |
Comparison of BWR fuel assembly options for minor actinide recycling
|
Martinez, Eduardo |
|
2019 |
132 |
C |
p. 288-298 |
artikel |
13 |
Comparison of loop seal clearing behavior between SBLOCA and SBO-related tests in the ATLAS facility
|
Kim, Yeon-Sik |
|
2019 |
132 |
C |
p. 734-740 |
artikel |
14 |
Concrete ablation analysis for molten corium-concrete interaction mitigation strategy
|
Kim, Ji-Hun |
|
2019 |
132 |
C |
p. 615-627 |
artikel |
15 |
Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors
|
Alzaben, Y. |
|
2019 |
132 |
C |
p. 70-81 |
artikel |
16 |
Coupling RMC and CFD for simulation of transients in TREAT reactor
|
Rao, Junjie |
|
2019 |
132 |
C |
p. 249-257 |
artikel |
17 |
Design an anti-windup controller for a PWR power-level control in the presence of control rod speed saturation
|
Eliasi, H. |
|
2019 |
132 |
C |
p. 415-426 |
artikel |
18 |
Development of a droplet entrainment rate model for a vertical adiabatic two-phase flow
|
Han, Kum Ho |
|
2019 |
132 |
C |
p. 181-190 |
artikel |
19 |
Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification
|
Kim, Kang Seog |
|
2019 |
132 |
C |
p. 1-23 |
artikel |
20 |
Development of thermal-hydraulic analysis code of a helically coiled once-through steam generator based on two-fluid model
|
Chen, Huandong |
|
2019 |
132 |
C |
p. 773-783 |
artikel |
21 |
Dispersion of radionuclides released by nuclear accident and dose assessment in the Greater Bay Area of China
|
Cai, Junjie |
|
2019 |
132 |
C |
p. 593-602 |
artikel |
22 |
Dynamic frequency response of a single-phase natural circulation loop under an imposed sinusoidal excitation
|
Basu, Dipankar N. |
|
2019 |
132 |
C |
p. 603-614 |
artikel |
23 |
Editorial Board
|
|
|
2019 |
132 |
C |
p. ii |
artikel |
24 |
Effect of gas pressure and bias potential on oxidation resistance of Cr coatings
|
He, Xiujie |
|
2019 |
132 |
C |
p. 243-248 |
artikel |
25 |
Effect of mesh refinement on the estimation of model input parameters using Inverse Uncertainty Quantification
|
Abu Saleem, Rabie A. |
|
2019 |
132 |
C |
p. 271-276 |
artikel |
26 |
Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors
|
George, Nathan M. |
|
2019 |
132 |
C |
p. 486-503 |
artikel |
27 |
Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas
|
Yoo, Hee Sang |
|
2019 |
132 |
C |
p. 108-118 |
artikel |
28 |
Improvement of few-group cross-section generation in fast reactor analysis system SARAX
|
Wei, Linfang |
|
2019 |
132 |
C |
p. 149-160 |
artikel |
29 |
Influencing factors on situation assessment of human operators in unexpected plant conditions
|
Kim, Tae Jin |
|
2019 |
132 |
C |
p. 526-536 |
artikel |
30 |
Investigation of uncertainty quantification methods for constitutive models and the application to LOFT LBLOCA
|
Xiong, Qingwen |
|
2019 |
132 |
C |
p. 119-133 |
artikel |
31 |
Investigation on flow instability in a natural circulation loop with rod bundles
|
Li, Zongyang |
|
2019 |
132 |
C |
p. 212-226 |
artikel |
32 |
Investigation on the role of mass flow rate in UTSG reverse flow under natural circulation condition
|
Xu, Zhigang |
|
2019 |
132 |
C |
p. 763-772 |
artikel |
33 |
Low-order multiphysics coupling techniques for nuclear reactor applications
|
Walker, Erik D. |
|
2019 |
132 |
C |
p. 327-338 |
artikel |
34 |
Measurement of kinetic parameter of the Jordan research and training reactor
|
Park, Beomwoo |
|
2019 |
132 |
C |
p. 322-326 |
artikel |
35 |
Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes
|
Nikitin, E. |
|
2019 |
132 |
C |
p. 679-685 |
artikel |
36 |
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches
|
Cervi, Eric |
|
2019 |
132 |
C |
p. 227-235 |
artikel |
37 |
Nuclear isotopic fissile content assay
|
Lee, YongDeok |
|
2019 |
132 |
C |
p. 82-86 |
artikel |
38 |
Numerical study of the stratification erosion benchmark for NPPs containment using CFD code GASFLOW-MPI
|
Zhang, Han |
|
2019 |
132 |
C |
p. 199-211 |
artikel |
39 |
On the prompt time eigenvalue estimation for subcritical multiplying systems
|
Chentre, N. |
|
2019 |
132 |
C |
p. 172-180 |
artikel |
40 |
On the white boundary condition in Monte Carlo simulation
|
She, Ding |
|
2019 |
132 |
C |
p. 413-414 |
artikel |
41 |
Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators
|
Guo, H. |
|
2019 |
132 |
C |
p. 713-722 |
artikel |
42 |
Overview of the experimental studies and numerical simulations on the filtered containment venting systems with wet scrubbers
|
Dong, Shichang |
|
2019 |
132 |
C |
p. 461-485 |
artikel |
43 |
Performance analysis of magnetohydrodynamic pump for sodium-cooled fast reactor thermal hydraulic experiment
|
Kwak, Jaesik |
|
2019 |
132 |
C |
p. 191-198 |
artikel |
44 |
Performance evaluation of a low flow rate Annular Linear Induction Pump
|
Sharma, Prashant |
|
2019 |
132 |
C |
p. 299-310 |
artikel |
45 |
Physico-chemical characteristics of graphite aerosols generated during postulated air ingress accident
|
Yadav, S.K. |
|
2019 |
132 |
C |
p. 100-107 |
artikel |
46 |
PIV measurement of turbulent flow downstream of mixing vane spacer grid in 5×5 rod bundle
|
Qu, Wenhai |
|
2019 |
132 |
C |
p. 277-287 |
artikel |
47 |
Prediction of flow distribution of vertical upward co-current adiabatic annular flow in 8 × 8 rod bundle
|
Ju, Peng |
|
2019 |
132 |
C |
p. 555-562 |
artikel |
48 |
Predictive control modeling of ADS’s MEBT using BPNN to reduce the impact of noise on the control system
|
Yang, Xuhui |
|
2019 |
132 |
C |
p. 576-583 |
artikel |
49 |
Preliminary investigation on the melting behavior of a freeze-valve for the Molten Salt Fast Reactor
|
Tiberga, Marco |
|
2019 |
132 |
C |
p. 544-554 |
artikel |
50 |
Reducing the number of training samples for transient classification in nuclear power plant
|
Prusty, Manas Ranjan |
|
2019 |
132 |
C |
p. 702-712 |
artikel |
51 |
Review of research progress on flow and rupture characteristics of liquid film on corrugated plate wall
|
Wang, Bo |
|
2019 |
132 |
C |
p. 741-751 |
artikel |
52 |
Sensitivity uncertainty analysis and new neutron capture cross-sections for gadolinium odd-isotopes to support nuclear safety
|
Rocchi, Federico |
|
2019 |
132 |
C |
p. 537-543 |
artikel |
53 |
SGSD: A novel Sequential Gamma-ray Spectrum Deconvolution algorithm
|
Shahabinejad, Hadi |
|
2019 |
132 |
C |
p. 369-380 |
artikel |
54 |
Spatial decomposition of structured grids for nuclear reactor simulations
|
Fitzgerald, Andrew P. |
|
2019 |
132 |
C |
p. 686-701 |
artikel |
55 |
Spatially dependent embedded self-shielding method for nonuniform temperature distribution
|
Kim, Kang Seog |
|
2019 |
132 |
C |
p. 563-575 |
artikel |
56 |
Stability preservation in the numerical treatment of a nuclear reactor
|
Zarei, M. |
|
2019 |
132 |
C |
p. 339-346 |
artikel |
57 |
Steam condensation on a downward-facing plate in presence of air
|
Chen, Ronghua |
|
2019 |
132 |
C |
p. 451-460 |
artikel |
58 |
Supercritical steam generator design and thermal analysis based on HTR-PM
|
Zhang, Zhen |
|
2019 |
132 |
C |
p. 311-321 |
artikel |
59 |
Synthesis of pool modeling of fast reactors in system dynamics codes
|
Natesan, K. |
|
2019 |
132 |
C |
p. 24-33 |
artikel |
60 |
The application of radial basis function interpolation in reactor core power distribution on-line monitoring
|
Peng, Xingjie |
|
2019 |
132 |
C |
p. 752-762 |
artikel |
61 |
The benchmark experiment on slab iron with D-T neutrons for validation of evaluated nuclear data
|
Ding, Yanyan |
|
2019 |
132 |
C |
p. 236-242 |
artikel |
62 |
The comparison between nonlinear and linear preconditioning JFNK method for transient neutronics/thermal-hydraulics coupling problem
|
Zhang, Han |
|
2019 |
132 |
C |
p. 357-368 |
artikel |
63 |
The flow transition characteristics of supercritical CO2 based closed natural circulation loop (NCL) system
|
Deng, Bili |
|
2019 |
132 |
C |
p. 134-148 |
artikel |
64 |
Thermal sizing design and experimental evaluation of molten salt-to-air heat exchanger
|
Chen, Yu-Shuang |
|
2019 |
132 |
C |
p. 504-511 |
artikel |
65 |
Thermal stratification and mixing in a Nordic BWR pressure suppression pool
|
Gallego-Marcos, Ignacio |
|
2019 |
132 |
C |
p. 442-450 |
artikel |
66 |
The SCALE/AMPX multigroup cross section processing for fast reactor analysis
|
Kim, Kang Seog |
|
2019 |
132 |
C |
p. 161-171 |
artikel |
67 |
Treatment of human and organizational factors for multi-unit HRA: Application of SPAR-H method
|
Park, Jooyoung |
|
2019 |
132 |
C |
p. 656-678 |
artikel |
68 |
Uncertainty analysis of rod ejection accident in VVER-1000 reactor
|
Miglierini, Bruno |
|
2019 |
132 |
C |
p. 628-635 |
artikel |
69 |
U3Si2-SiC fuel performance analysis in BISON during normal operation
|
Li, Wei |
|
2019 |
132 |
C |
p. 34-45 |
artikel |
70 |
Validating an adaptive time step scheme for the neutron diffusion equation with the UMass-Lowell Research Reactor kinetics data
|
Boffie, J. |
|
2019 |
132 |
C |
p. 404-412 |
artikel |
71 |
Verification of safety critical and control systems of Nuclear Power Plants using Petri nets
|
Singh, Pooja |
|
2019 |
132 |
C |
p. 584-592 |
artikel |