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                             130 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Absolute burnup measurement of LEU silicide fuel plate irradiated in the RSG GAS multipurpose reactor by destructive radiochemical technique Ginting, Aslina Br.
 2015
 85 C p. 613-620
8 p.
 artikel
2 A characteristic correlation for heat transfer over serrated finned tubes Anoop, B.
 2015
 85 C p. 1052-1065
14 p.
 artikel
3 A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT Aufiero, Manuele
 2015
 85 C p. 245-258
14 p.
 artikel
4 A correction and a clarification to “Optimizing variance reduction in Monte Carlo eigenvalue calculations that employ the source iteration approach” Burn, Kenneth W.
 2015
 85 C p. 776-777
2 p.
 artikel
5 Adjustment method of deterministic control rods worth computation based on measurements and auxiliary Monte Carlo runs Wang, Guan-bo
 2015
 85 C p. 183-192
10 p.
 artikel
6 A domain-specific analysis system for examining nuclear reactor simulation data for light-water and sodium-cooled fast reactors Billings, Jay Jay
 2015
 85 C p. 856-868
13 p.
 artikel
7 A MELCOR model of Fukushima Daiichi Unit 1 accident Sevón, Tuomo
 2015
 85 C p. 1-11
11 p.
 artikel
8 A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN Isotalo, A.E.
 2015
 85 C p. 68-77
10 p.
 artikel
9 Analysis of a fatal accident in a highly enriched uranium facility Difilippo, Felix C.
 2015
 85 C p. 909-916
8 p.
 artikel
10 Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident Hung, Zhen-Yu
 2015
 85 C p. 717-724
8 p.
 artikel
11 Analysis of Doppler coefficients for typical PWR UO2 and MTR U3Si2-Al fuels using ENDF/B-VI and VII Kim, Kyung-O
 2015
 85 C p. 1024-1028
5 p.
 artikel
12 Analysis of minor actinides transmutation for a Molten Salt Fast Reactor Yu, Chenggang
 2015
 85 C p. 597-604
8 p.
 artikel
13 Analysis of propagating temperature perturbations in the primary circuit of PWRs Kiss, Sándor
 2015
 85 C p. 1167-1174
8 p.
 artikel
14 Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF Cong, Tenglong
 2015
 85 C p. 127-136
10 p.
 artikel
15 Analysis on the characteristics of geologic disposal waste arising from various partitioning and conditioning options Liang, Fan
 2015
 85 C p. 371-379
9 p.
 artikel
16 A neutronic design study of lead-bismuth-cooled small and safe ultra-long-life cores Hong, Ser Gi
 2015
 85 C p. 58-67
10 p.
 artikel
17 An evaluation of the design and performance for a new neutron absorber based on an artificial rare-earth compound Kim, Song Hyun
 2015
 85 C p. 461-466
6 p.
 artikel
18 A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis Kumar, Akansha
 2015
 85 C p. 27-35
9 p.
 artikel
19 An improved assembly homogenization approach for plate-type research reactor Ma, Jimin
 2015
 85 C p. 1003-1013
11 p.
 artikel
20 A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis Cho, Bumhee
 2015
 85 C p. 937-957
21 p.
 artikel
21 An optimized process for tritium-containing waste water collection of High-Temperature Gas-cooled Reactor Chang, Hua
 2015
 85 C p. 311-316
6 p.
 artikel
22 A novel coordinated control for Integrated Pressurized Water Reactor Zhao, Yuxin
 2015
 85 C p. 1029-1034
6 p.
 artikel
23 A Novel gamma emission tomography instrument for enhanced fuel characterization capabilities within the OECD Halden Reactor Project Holcombe, Scott
 2015
 85 C p. 837-845
9 p.
 artikel
24 A numerical study on local fuel–coolant interactions in a simulated molten fuel pool using the SIMMER-III code Cheng, Songbai
 2015
 85 C p. 740-752
13 p.
 artikel
25 AP1000® Large-Break LOCA BEPU analysis with TRACE code Queral, C.
 2015
 85 C p. 576-589
14 p.
 artikel
26 Application of a new passive acoustic leak detection approach to recordings from the Dounreay prototype fast reactor Marklund, Anders Riber
 2015
 85 C p. 175-182
8 p.
 artikel
27 Application of Data Reconciliation and Fault Detection and Isolation of Ion Chambers in Advanced Heavy Water Reactor Yellapu, V.S.
 2015
 85 C p. 1210-1225
16 p.
 artikel
28 Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR Pecchia, Marco
 2015
 85 C p. 271-278
8 p.
 artikel
29 Application of the “best representativity” method to a PWR fuel calculation using the critical experiments at the Toshiba NCA facility Umano, Takuya
 2015
 85 C p. 78-92
15 p.
 artikel
30 A two dimensional approach for temperature distribution in reactor lower head during severe accident Cao, Zhen
 2015
 85 C p. 467-480
14 p.
 artikel
31 BELLA: a multi-point dynamics code for safety-informed design of fast reactors Bortot, S.
 2015
 85 C p. 228-235
8 p.
 artikel
32 Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology Matijević, Mario
 2015
 85 C p. 979-994
16 p.
 artikel
33 Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods Liu, Shichang
 2015
 85 C p. 830-836
7 p.
 artikel
34 Burnup instabilities in the full-core HTR model simulation Kępisty, Grzegorz
 2015
 85 C p. 652-661
10 p.
 artikel
35 BWR Mark III containment analyses using a GOTHIC 8.0 3D model Jimenez, Gonzalo
 2015
 85 C p. 687-703
17 p.
 artikel
36 BWR MARK I pressure suppression pool mixing and stratification analysis using GOTHIC lumped parameter modeling methodology Ozdemir, Ozkan Emre
 2015
 85 C p. 532-543
12 p.
 artikel
37 Calculation of the spallation target neutronic parameters in Accelerator Driven Subcritical TRIGA reactor Hassanzadeh, M.
 2015
 85 C p. 326-330
5 p.
 artikel
38 CFD analysis of hydrogen volumetric concentrations in a Hard Venting Containment System of a Mark II BWR Gómez-Torres, Armando Miguel
 2015
 85 C p. 552-565
14 p.
 artikel
39 CFD simulation for thermal mixing of a SMART flow mixing header assembly Kim, Young In
 2015
 85 C p. 357-370
14 p.
 artikel
40 Code development for eigenvalue total sensitivity analysis and total uncertainty analysis Wan, Chenghui
 2015
 85 C p. 788-797
10 p.
 artikel
41 Comparative study of different concrete composition as gamma-ray shielding materials Waly, El-Sayed A.
 2015
 85 C p. 306-310
5 p.
 artikel
42 Comparison of transient analysis of LBE-cooled fast reactor and ADS under loss of heat sink accident Wang, Gang
 2015
 85 C p. 494-500
7 p.
 artikel
43 Computer analyses on loop seal clearing experiment at PWR PACTEL Kauppinen, Otso-Pekka
 2015
 85 C p. 47-57
11 p.
 artikel
44 Computing adjoint-weighted kinetics parameters in Tripoli-4® by the Iterated Fission Probability method Truchet, Guillaume
 2015
 85 C p. 17-26
10 p.
 artikel
45 Convex-based void filling method for CAD-based Monte Carlo geometry modeling Yu, Shengpeng
 2015
 85 C p. 380-385
6 p.
 artikel
46 Design and performance of 2D and 3D-shuffled breed-and-burn cores Qvist, Staffan
 2015
 85 C p. 93-114
22 p.
 artikel
47 Design and tuning of a Decentralized Fuzzy Logic Controller for a MIMO type Pressurized Heavy Water Reactor Wallam, Fahad
 2015
 85 C p. 1104-1114
11 p.
 artikel
48 Detection of coolant void in lead-cooled fast reactors Wolniewicz, Peter
 2015
 85 C p. 1096-1103
8 p.
 artikel
49 Development of a sensitivity and uncertainty analysis code for high temperature gas-cooled reactor physics based on the generalized perturbation theory Han, Tae Young
 2015
 85 C p. 501-511
11 p.
 artikel
50 Development of a simulation platform for dynamic simulation and control studies of AP1000 nuclear steam supply system Wan, Jiashuang
 2015
 85 C p. 704-716
13 p.
 artikel
51 Development of random geometry capability in RMC code for stochastic media analysis Liu, Shichang
 2015
 85 C p. 903-908
6 p.
 artikel
52 Dynamic Monte Carlo calculation method by solving frequency domain transport equation using the complex-valued weight Monte Carlo method Yamamoto, Toshihiro
 2015
 85 C p. 426-433
8 p.
 artikel
53 Editorial board 2015
 85 C p. IFC-
1 p.
 artikel
54 Effective atomic number of selected construction materials using gamma backscattering technique Kiran, K.U.
 2015
 85 C p. 1077-1084
8 p.
 artikel
55 Effects of cross sections library parameters on the OECD/NEA Oskarshamn-2 benchmark solution Balestra, P.
 2015
 85 C p. 643-651
9 p.
 artikel
56 Equivalent mechanical model for structural dynamic analysis of elevated tank like AP1000 PCCWST Liu, Yu
 2015
 85 C p. 1175-1183
9 p.
 artikel
57 Estimating the response times of human operators working in the main control room of nuclear power plants based on the context of a seismic event – A case study Park, Jinkyun
 2015
 85 C p. 36-46
11 p.
 artikel
58 Evaluation of RCS injection strategy by normal residual heat removal system in severe accident management Zou, J.
 2015
 85 C p. 166-174
9 p.
 artikel
59 Evaluation of subcritical hybrid systems loaded with reprocessed fuel Velasquez, Carlos E.
 2015
 85 C p. 633-642
10 p.
 artikel
60 Experimental and numerical investigations on roof slab of a pool type sodium cooled fast reactor based on model studies Venugopal, Prabhu Raja
 2015
 85 C p. 1085-1095
11 p.
 artikel
61 Experimental investigation of heat removal performance of a concrete storage cask Bang, Kyoung-Sik
 2015
 85 C p. 679-686
8 p.
 artikel
62 Fault detection and isolation for self powered neutron detectors based on Principal Component Analysis Peng, Xingjie
 2015
 85 C p. 213-219
7 p.
 artikel
63 Feasibility assessment of the once-through thorium fuel cycle for the PTVM LWR concept Rachamin, R.
 2015
 85 C p. 1119-1130
12 p.
 artikel
64 Fukushima Daiichi Unit 1 power plant containment analysis using GOTHIC Ozdemir, Ozkan Emre
 2015
 85 C p. 621-632
12 p.
 artikel
65 Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor Siefman, Daniel J.
 2015
 85 C p. 434-443
10 p.
 artikel
66 Fuzzy probability based fault tree analysis to propagate and quantify epistemic uncertainty Purba, Julwan Hendry
 2015
 85 C p. 1189-1199
11 p.
 artikel
67 Heterogeneous BN equations and symmetries Tommasi, J.
 2015
 85 C p. 145-158
14 p.
 artikel
68 Hydraulic lift-off issues for application of high performance annular fuels in pressurized water reactors Rahman, Mohammad Mizanur
 2015
 85 C p. 1018-1023
6 p.
 artikel
69 Identifying objective criterion to determine a complicated task – A comparative study Park, Jinkyun
 2015
 85 C p. 205-212
8 p.
 artikel
70 Impact of the moderation ratio over the performance of different BWR fuel assemblies Alonso, Gustavo
 2015
 85 C p. 670-678
9 p.
 artikel
71 Improved diffusion layer model based on real gas state equation for high pressure condensation Wu, Lei
 2015
 85 C p. 444-452
9 p.
 artikel
72 Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool Fu, Wen
 2015
 85 C p. 346-356
11 p.
 artikel
73 Investigation of different scenarios of thorium–uranium fuel distribution in the VVER-1200 first core Dwiddar, Mohammed S.
 2015
 85 C p. 605-612
8 p.
 artikel
74 Kinematics analysis and verification of In-Vessel Fuel Handling System for China Lead-based Research Reactor Zeng, Meihua
 2015
 85 C p. 301-305
5 p.
 artikel
75 Linear regression and sensitivity analysis in nuclear reactor design Kumar, Akansha
 2015
 85 C p. 798-811
14 p.
 artikel
76 Measurement and simulation of the neutron flux distribution in the TRIGA Mark II reactor core Chiesa, Davide
 2015
 85 C p. 925-936
12 p.
 artikel
77 Modeling and experimental studies on mixing and stratification during natural convection in containments Zhang, He
 2015
 85 C p. 317-325
9 p.
 artikel
78 Modeling of the radiation doses during dismantling of RBMK-1500 reactor emergency core cooling system large diameter pipes Simonis, Audrius
 2015
 85 C p. 159-165
7 p.
 artikel
79 Model of the IBR-2M pulsed reactor dynamics for investigating transition processes in a wide range of power variation Pepyolyshev, Yu.N.
 2015
 85 C p. 488-493
6 p.
 artikel
80 Monte Carlo simulations of periodic pulsed reactor with moving geometry parts Cao, Yan
 2015
 85 C p. 236-244
9 p.
 artikel
81 Monte Carlo solver for UWB1 nuclear fuel depletion code Lovecký, M.
 2015
 85 C p. 778-787
10 p.
 artikel
82 More conservative governing equations in RELAP5: Derivation of equations Fu, Zheng
 2015
 85 C p. 523-531
9 p.
 artikel
83 MOX fuel enrichment prediction in PWR using polynomial models Mouginot, B.
 2015
 85 C p. 812-819
8 p.
 artikel
84 Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions Wu, Xu
 2015
 85 C p. 763-775
13 p.
 artikel
85 Neutron spectrum kinetics in the infinite homogeneous reactor Dall’Osso, Aldo
 2015
 85 C p. 662-669
8 p.
 artikel
86 Novel modular natural circulation BWR design and safety evaluation Ishii, Mamoru
 2015
 85 C p. 220-227
8 p.
 artikel
87 Nuclear power plant instabilities analysis Gavilan Moreno, Carlos J.
 2015
 85 C p. 279-289
11 p.
 artikel
88 Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers Zimmermann, Markus
 2015
 85 C p. 403-417
15 p.
 artikel
89 Numerical simulation and theoretical analysis of heat transfer in a moving packed bed with the local internal heat source Wang, Yongwei
 2015
 85 C p. 418-425
8 p.
 artikel
90 Numerical simulation of heat transfer and friction in non-uniform wall roughness lattice with different roughness element shapes Xiao, Hongguang
 2015
 85 C p. 732-739
8 p.
 artikel
91 On the spatiotemporal correlations in a linear stochastic field generated by non-interacting particles: Theory Ayyoubzadeh, Seyed Mohsen
 2015
 85 C p. 1226-1238
13 p.
 artikel
92 On the use of the SPH method in nodal diffusion analyses of SFR cores Nikitin, E.
 2015
 85 C p. 544-551
8 p.
 artikel
93 On the way to enabling FRAPCON-3 to model spent fuel under dry storage conditions: The thermal evolution Feria, F.
 2015
 85 C p. 995-1002
8 p.
 artikel
94 Optimization of U–Th fuel in heavy water moderated thermal breeder reactors using multivariate regression analysis and genetic algorithms Kumar, Akansha
 2015
 85 C p. 885-892
8 p.
 artikel
95 Optimized CANDU-6 cell and reactivity device supercell models for advanced fuels reactor database generation St-Aubin, Emmanuel
 2015
 85 C p. 331-336
6 p.
 artikel
96 Parametric evaluation of an SMR design domain Al Rashdan, Ahmad
 2015
 85 C p. 958-978
21 p.
 artikel
97 Prediction of the strength of concrete radiation shielding based on LS-SVM Juncai, Xu
 2015
 85 C p. 296-300
5 p.
 artikel
98 Prediction of time series of NPP operating parameters using dynamic model based on BP neural network Liu, Yong-kuo
 2015
 85 C p. 566-575
10 p.
 artikel
99 Preliminary study on functional performance of compound type multistage safety injection tank Bae, Youngmin
 2015
 85 C p. 1045-1051
7 p.
 artikel
100 Preliminary test results and CFD analysis for Moderator Circulation Test (MCT) Kim, Hyoung Tae
 2015
 85 C p. 386-393
8 p.
 artikel
101 Preparation of U3O8 by calcination from ammonium uranyl carbonate in microwave fields: Process optimization Liu, Bing-Guo
 2015
 85 C p. 879-884
6 p.
 artikel
102 Pressure drops of single/two-phase flows through porous beds with multi-sizes spheres and sands particles Li, Liangxing
 2015
 85 C p. 290-295
6 p.
 artikel
103 Pressure oscillation and steam cavity during the condensation of a submerged steam jet Zhao, Quanbin
 2015
 85 C p. 512-522
11 p.
 artikel
104 Proliferation issues related to fast SMRs Frieß, Friederike
 2015
 85 C p. 725-731
7 p.
 artikel
105 Proof-of-principle of high-fidelity coupled CRUD deposition and cycle depletion simulation Walter, Daniel J.
 2015
 85 C p. 1152-1166
15 p.
 artikel
106 Reactivity estimation during a reactivity-initiated accident using the extended Kalman filter Busquim e Silva, R.
 2015
 85 C p. 753-762
10 p.
 artikel
107 Results of nuclear security culture survey on personnel at nuclear power plants Yoo, Hosik
 2015
 85 C p. 398-402
5 p.
 artikel
108 Screening key parameters related to passive system performance based on Analytic Hierarchy Process Ma, Guohang
 2015
 85 C p. 1141-1151
11 p.
 artikel
109 Semi-analytic benchmark for multi-group free-gas Legendre moments and the application of Gauss quadrature in generating thermal scattering Legendre moments Zheng, Weixiong
 2015
 85 C p. 1131-1140
10 p.
 artikel
110 Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism Wang, Jun
 2015
 85 C p. 193-204
12 p.
 artikel
111 Simultaneous multiple reactivity insertions in a typical MTR-type research reactor having U3Si2–Al fuel Nasir, Rubina
 2015
 85 C p. 869-878
10 p.
 artikel
112 Space–time effects in the initiating phase of sodium fast reactors and their evaluation using a three-dimensional neutron kinetics model Guyot, M.
 2015
 85 C p. 115-126
12 p.
 artikel
113 Spatially adaptive hp refinement approach for PN neutron transport equation using spectral element method Nahavandi, N.
 2015
 85 C p. 1066-1076
11 p.
 artikel
114 Stability monitor for Boiling Water Reactors based on the Multivariate Empirical Mode Decomposition Prieto-Guerrero, Alfonso
 2015
 85 C p. 453-460
8 p.
 artikel
115 Study the effects of different reflector types on the neutronic parameters of the 10MW MTR reactor using the MCNP4C code Dawahra, S.
 2015
 85 C p. 1115-1118
4 p.
 artikel
116 Techno-economic assessment of thorium power in Canada Graves, Brian
 2015
 85 C p. 481-487
7 p.
 artikel
117 The characteristics of break flows of SBLOCA tests in ATLAS facility Kim, Yeon-Sik
 2015
 85 C p. 1200-1209
10 p.
 artikel
118 The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP Shi, Er-bing
 2015
 85 C p. 590-596
7 p.
 artikel
119 The new STRESA tool for preservation of thermalhydraulic experimental data produced in the European Commission Pla, Patricia
 2015
 85 C p. 893-902
10 p.
 artikel
120 Theoretical calculation of the characteristics of annular flow in a rectangular narrow channel Chen, Chong
 2015
 85 C p. 259-270
12 p.
 artikel
121 Thermal–mechanical analysis of the first wall for CFETR helium cooled solid breeder blanket Liu, Qianwen
 2015
 85 C p. 12-16
5 p.
 artikel
122 Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data Dupré, A.
 2015
 85 C p. 820-829
10 p.
 artikel
123 Transient behavior studies of TRIGA core for variations in reactor kinetics Badrun, N.H.
 2015
 85 C p. 394-397
4 p.
 artikel
124 Transient Fission Matrix: Kinetic calculation and kinetic parameters β eff and Λ eff calculation Laureau, A.
 2015
 85 C p. 1035-1044
10 p.
 artikel
125 Uncertainty quantification of total delayed neutron yields and time-dependent delayed neutron emission rates in frame of summation calculations Chiba, Go
 2015
 85 C p. 846-855
10 p.
 artikel
126 Validation of hydrogen gas stratification and mixing models Wu, Hsingtzu
 2015
 85 C p. 137-144
8 p.
 artikel
127 Validation study of the reactor physics lattice transport code WIMSD-5B by TRX and BAPL critical experiments of light water reactors Khan, M.J.H.
 2015
 85 C p. 1014-1017
4 p.
 artikel
128 Velocity characteristic and stability of wave solutions for a candle reactor with thermal feedback Khotyayintsev, Volodymyr M.
 2015
 85 C p. 337-345
9 p.
 artikel
129 Weapons Grade Plutonium utilization with fertile materials in a Gas Turbine-Modular Helium Reactor Erol, Özgür
 2015
 85 C p. 917-924
8 p.
 artikel
130 Weighted-delta-tracking for Monte Carlo particle transport Morgan, L.W.G.
 2015
 85 C p. 1184-1188
5 p.
 artikel
                             130 gevonden resultaten
 
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