Digitale Bibliotheek
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                             71 gevonden resultaten
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
                             71 gevonden resultaten
 
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