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                             88 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Activation of 197Au and 209Bi in a fast spectrum sub-critical assembly composed of 500kg natural uranium irradiated with 1 and 4GeV deuterons Asquith, N.L.
2014
63 C p. 742-750
9 p.
artikel
2 A deterministic and Monte Carlo coupling method for PWR cavity radiation streaming calculation Zheng, Zheng
2014
63 C p. 162-171
10 p.
artikel
3 A direct methodology to establish design requirements for human–system interface (HSI) of automatic systems in nuclear power plants Anuar, Nuraslinda
2014
63 C p. 326-338
13 p.
artikel
4 Alpha eigenvalue calculations with Tripoli-4® Zoia, Andrea
2014
63 C p. 276-284
9 p.
artikel
5 A molecular dynamics study about graphite and boron coated graphite at reactor temperatures Korkut, Turgay
2014
63 C p. 100-106
7 p.
artikel
6 A multi-level surface rebalancing approach for efficient convergence acceleration of 3D full core multi-group fine grid nodal diffusion iterations van Geemert, René
2014
63 C p. 22-37
16 p.
artikel
7 An adaptive p-refinement strategy applied to nodal expansion method in 3D Cartesian geometry Poursalehi, N.
2014
63 C p. 575-586
12 p.
artikel
8 An advancement in iterative solution schemes for three-dimensional, two-fluid modeling of two-phase flow in PWR fuel bundles Mohitpour, Maryam
2014
63 C p. 83-99
17 p.
artikel
9 An alternative stochastic formulation for the point reactor Ayyoubzadeh, Seyed Mohsen
2014
63 C p. 691-695
5 p.
artikel
10 Analysis of an ATLAS 6-in. cold-leg break simulation with MARS code Kim, Seyun
2014
63 C p. 268-275
8 p.
artikel
11 Analytical benchmark for non-equilibrium radiation diffusion in finite size systems Ghosh, Karabi
2014
63 C p. 59-68
10 p.
artikel
12 Analytical Dancoff factor evaluations for reactor designs loaded with TRISO particle fuel Ji, Wei
2014
63 C p. 665-673
9 p.
artikel
13 An experimental investigation of loop seal clearings in SBLOCA tests Kim, Yeon-Sik
2014
63 C p. 721-730
10 p.
artikel
14 An experimental study on geysering phenomena induced by buoyancy in a heating system Tong, L.L.
2014
63 C p. 129-137
9 p.
artikel
15 A pragmatic approach to estimate alpha factors for common cause failure analysis Hassija, Varun
2014
63 C p. 317-325
9 p.
artikel
16 Assessing the SCRRI and RIP runback performances of TRACE/PARCS for Lungmen ABWR Chang, Chia-Ying
2014
63 C p. 1-8
8 p.
artikel
17 A study on ground-state energies of nuclei by using neural networks Bayram, Tuncay
2014
63 C p. 172-175
4 p.
artikel
18 Benchmark analysis of fission-rate distributions in a series of spherical depleted-uranium assemblies for hybrid-reactor design Zhu, T.H.
2014
63 C p. 486-490
5 p.
artikel
19 Calculation and analysis for p+ 50,52,53,54,natCr reactions Pan, Hui
2014
63 C p. 446-460
15 p.
artikel
20 Calculation of half-value thickness for aluminum absorbers by means of fractional calculus Şen, Mürsel
2014
63 C p. 46-50
5 p.
artikel
21 Calculation of VVER-1000 reactor scaling factor for inference of core barrel motion Fallah, Vahid Farhang
2014
63 C p. 205-208
4 p.
artikel
22 Can corrosion and CRUD actually improve safety margins in LWRs? Buongiorno, Jacopo
2014
63 C p. 9-21
13 p.
artikel
23 Characterization of a spent-fuel-pit rupture based on water-level monitoring Matkovič, Marko
2014
63 C p. 674-679
6 p.
artikel
24 Comparative safety assessment of HEU and LEU core of MNSR under large reactivity insertion accidents Hainoun, A.
2014
63 C p. 624-632
9 p.
artikel
25 Comparing neutronics codes performance in analyzing a fresh-fuelled research reactor core Savva, P.
2014
63 C p. 731-741
11 p.
artikel
26 Comparison of heuristic optimization techniques for the enrichment and gadolinia distribution in BWR fuel lattices and decision analysis Castillo, Alejandro
2014
63 C p. 556-564
9 p.
artikel
27 Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures Trinuruk, Piyatida
2014
63 C p. 437-445
9 p.
artikel
28 Design of a photoneutron source based on 10MeV electrons of radiotherapy linac Tatari, M.
2014
63 C p. 69-74
6 p.
artikel
29 Determination of shielding parameters for different types of resins Elmahroug, Y.
2014
63 C p. 619-623
5 p.
artikel
30 Determination of the LEU core safety parameters of the MNSR reactor using the MCNP4C code Dawahra, S.
2014
63 C p. 594-597
4 p.
artikel
31 Determining the water content in concrete by gamma scattering method Priyada, P.
2014
63 C p. 565-570
6 p.
artikel
32 Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment Zheng, Meiyin
2014
63 C p. 491-498
8 p.
artikel
33 Development of impedance void meter for evaluation of flow symmetry Schlegel, J.P.
2014
63 C p. 525-532
8 p.
artikel
34 Distribution characteristics of radionuclides in high-temperature melt phase during melt decontamination of decommissioned metal waste Min, Byung-Youn
2014
63 C p. 774-779
6 p.
artikel
35 1-D modeling of radionuclide transport via heterogeneous geological formations for arbitrary length decay chains using numerical inversion of Laplace transforms van den Akker, Bret Patrick
2014
63 C p. 763-773
11 p.
artikel
36 Dynamic heat transfer performance study of steam generator based on distributed parameter method Zhang, Guolei
2014
63 C p. 658-664
7 p.
artikel
37 Editorial board 2014
63 C p. IFC-
1 p.
artikel
38 Effective spatial mapping for coupled code analysis of thermal-hydraulics/neutron-kinetics of boiling water reactors Peltonen, Joanna
2014
63 C p. 461-485
25 p.
artikel
39 Effect of core configuration on the burnup calculations of MTR research reactors Hussein, H.M.
2014
63 C p. 285-294
10 p.
artikel
40 Effect of steam-exhaust operation of secondary coolant circuit on ship reactor blackout accident Yang, Lei
2014
63 C p. 38-45
8 p.
artikel
41 Effects of delayed RCP trip during SBLOCA in PWR Montero-Mayorga, J.
2014
63 C p. 107-125
19 p.
artikel
42 Evaluation of alternative removal methods for decommissioning of heavy components in nuclear power plants Jeong, Kwan-Seong
2014
63 C p. 506-508
3 p.
artikel
43 Evaluation of debris bed self-leveling behavior: A simple empirical approach and its validations Cheng, Songbai
2014
63 C p. 188-198
11 p.
artikel
44 Experimental study on heat transfer of supercritical water flowing downward in circular tubes Zhao, M.
2014
63 C p. 339-349
11 p.
artikel
45 Experimental study on spray characteristics of pressure-swirl nozzles in pressurizer Lan, Zhike
2014
63 C p. 215-227
13 p.
artikel
46 Experimental study on the convective heat transfer enhancement in single-phase steam flow by a support grid Kim, Byoung Jae
2014
63 C p. 409-416
8 p.
artikel
47 Frequency domain Monte Carlo simulation method for cross power spectral density driven by periodically pulsed spallation neutron source using complex-valued weight Monte Carlo Yamamoto, Toshihiro
2014
63 C p. 711-720
10 p.
artikel
48 Importance of self-shielding for improving sensitivity coefficients in light water nuclear reactors Foad, Basma
2014
63 C p. 417-426
10 p.
artikel
49 Investigation of lead borate glasses doped with aluminium oxide as gamma ray shielding materials Kaur, Sandeep
2014
63 C p. 350-354
5 p.
artikel
50 Long-term pressure and temperature analysis and suppression pool mixing of Lungmen ABWR containment Chen, Yen-Shu
2014
63 C p. 598-611
14 p.
artikel
51 Measurement and estimation of isomeric cross section of 137Ba(n, n′)137mBa reaction using accelerator based neutron source Barough, M.S.
2014
63 C p. 209-214
6 p.
artikel
52 Measurement of effective neutron cross section of the reaction 98Mo (n, γ) 99Mo in TRR nuclear reactor by using thermal neutrons Jokar, A.R.
2014
63 C p. 653-657
5 p.
artikel
53 Measurement of the neutron capture cross-section of 238U at neutron energies of 5.9±0.5 and 15.5±0.7MeV by using the neutron activation technique Mulik, V.K.
2014
63 C p. 233-240
8 p.
artikel
54 Measurement of thermal neutron cross section and resonance integral for the 158Gd(n, γ)159Gd reaction by using a 55Mn monitor Karadag, Mustafa
2014
63 C p. 199-204
6 p.
artikel
55 Multi-dimensional pool analysis of Phenix end-of-life natural circulation test with MARS-LMR code Jeong, H.-Y.
2014
63 C p. 309-316
8 p.
artikel
56 Multi-group formulation of the temperature-dependent resonance scattering model and its impact on reactor core parameters Ghrayeb, Shadi Z.
2014
63 C p. 751-762
12 p.
artikel
57 Multimodel-based power-level control with state-feedback and observer for load-follow PWR core Li, Gang
2014
63 C p. 696-710
15 p.
artikel
58 Neutronic behavior of reactor moderated by mixtures of light and heavy waters at different ratios Nagy, Mohamed E.
2014
63 C p. 548-555
8 p.
artikel
59 Neutronic investigation of the application of certain plutonium-mixed fluids in a fusion–fission hybrid reactor Günay, Mehtap
2014
63 C p. 432-436
5 p.
artikel
60 Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor Blomeley, L.
2014
63 C p. 587-593
7 p.
artikel
61 Numerically stable Monte Carlo-burnup-thermal hydraulic coupling schemes Kotlyar, D.
2014
63 C p. 371-381
11 p.
artikel
62 Numerical prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant Wang, Chenglong
2014
63 C p. 633-645
13 p.
artikel
63 Numerical simulation of convection of argon gas in fast breeder reactor Nath, Dinesh
2014
63 C p. 51-58
8 p.
artikel
64 On normalization of fluxes and reaction rates in MCNP criticality calculations Žerovnik, Gašper
2014
63 C p. 126-128
3 p.
artikel
65 Optimization study for thermal efficiency of supercritical water reactor nuclear power plant Su, Yali
2014
63 C p. 541-547
7 p.
artikel
66 Overview of the standard problems of the ATLAS facility Kim, Yeon-Sik
2014
63 C p. 509-524
16 p.
artikel
67 Particle clustering in Monte Carlo criticality simulations Dumonteil, Eric
2014
63 C p. 612-618
7 p.
artikel
68 Pattern optimization of PWR reactor using hybrid parallel Artificial Bee Colony Safarzadeh, O.
2014
63 C p. 295-301
7 p.
artikel
69 Power level control of CANDLE reactor without control rods Sekimoto, Hiroshi
2014
63 C p. 427-431
5 p.
artikel
70 Predictive modeling of liquid-sodium thermal–hydraulics experiments and computations Arslan, Erkan
2014
63 C p. 355-370
16 p.
artikel
71 Radiological assessment for decommissioning of major component in nuclear power plants Jeong, Kwan-Seong
2014
63 C p. 571-574
4 p.
artikel
72 Radiological dose assessments according to dilution characteristics of radioactive materials in nuclear sites Jeong, Hyojoon
2014
63 C p. 261-267
7 p.
artikel
73 Real time analysis for atmospheric dispersions for Fukushima nuclear accident: Mobile phone based cloud computing assessment Woo, Tae Ho
2014
63 C p. 255-260
6 p.
artikel
74 Risk reduction approach to decommissioning hazards of nuclear facilities Jeong, Kwan-Seong
2014
63 C p. 382-386
5 p.
artikel
75 Sensitivity analysis of core neutronic parameters in accelerator driven subcritical reactors Hassanzadeh, M.
2014
63 C p. 228-232
5 p.
artikel
76 Simulation of some performance-related events of KALIMER-600 Seong, Seung-Hwan
2014
63 C p. 176-187
12 p.
artikel
77 Simulation of thermal stratification in BWR suppression pools with one dimensional modeling method Zhao, Haihua
2014
63 C p. 533-540
8 p.
artikel
78 Simulation of two-region and four-region models for typical PWR pressurizer and benchmark obtained results using available results Moghanaki, Samad Khani
2014
63 C p. 302-308
7 p.
artikel
79 Solution of the two dimensional diffusion and transport equations in a rectangular lattice with an elliptical fuel element using Fourier transform methods: One and two group cases Williams, M.M.R.
2014
63 C p. 146-156
11 p.
artikel
80 Study on flow pattern and separation performance of air–water swirl-vane separator Xiong, Zhenqin
2014
63 C p. 138-145
8 p.
artikel
81 Sufficient conditions for globally asymptotic self-stability of pressurized water reactors Dong, Zhe
2014
63 C p. 387-398
12 p.
artikel
82 Temperature coefficients calculation for the first fuel loading of NPP Mochovce 3–4 Vrban, Branislav
2014
63 C p. 646-652
7 p.
artikel
83 The closed thorium–transuranic fuel cycle in reduced-moderation PWRs and BWRs Lindley, Benjamin A.
2014
63 C p. 241-254
14 p.
artikel
84 The effect on radiation damage of structural material in a hybrid system by using a Monte Carlo radiation transport code Günay, Mehtap
2014
63 C p. 157-161
5 p.
artikel
85 The immersed body supermeshing method for modelling reactor physics problems with complex internal structures Buchan, A.G.
2014
63 C p. 399-408
10 p.
artikel
86 Theoretical investigations on two-phase flow instability in parallel channels under axial non-uniform heating Lu, Xiaodong
2014
63 C p. 75-82
8 p.
artikel
87 Three-dimension simulation of bubble behavior under nonlinear oscillation Zeng, Qingyun
2014
63 C p. 680-690
11 p.
artikel
88 Using genetic algorithms to calibrate the user-defined parameters of IIST model for SBLOCA analysis Tsai, Chiung-Wen
2014
63 C p. 499-505
7 p.
artikel
                             88 gevonden resultaten
 
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