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                             189 results found
no title author magazine year volume issue page(s) type
1 Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR Birchley, J.
2008
9 p. 2173-2181
9 p.
article
2 A CFD simulation process for fast reactor fuel assemblies Hamman, Kurt D.
2010
9 p. 2304-2312
9 p.
article
3 A comparative neutronic study of the standard HEU core and various potential LEU alternatives for a typical MNSR system Waqar, Sadaf
2008
9 p. 2302-2307
6 p.
article
4 A comparison between Japanese and French A16 defect assessment procedures for thermal fatigue crack growth Wakai, T.
2005
9 p. 937-944
8 p.
article
5 A computational study of the effect of distortions of the moderator cooling channel of the Advanced Gas-cooled Reactor He, S.
2005
9 p. 965-982
18 p.
article
6 A containment analysis for SBLOCA in the refurbished Wolsong-1 Nuclear Power Plant Kim, Tech-Mo
2011
9 p. 3804-3811
8 p.
article
7 ACSEPT—Partitioning technologies and actinide science: Towards pilot facilities in Europe Bourg, S.
2011
9 p. 3427-3435
9 p.
article
8 A droplet entrainment model based on the force balance of an interfacial wave in two-phase annular flow Ryu, Seok-Hee
2011
9 p. 3890-3897
8 p.
article
9 A fuel performance analysis for a 450MWth deep burn-high temperature reactor Kim, Young Min
2011
9 p. 3753-3760
8 p.
article
10 A heat transfer analysis of the CCI experiments 1–3 Sevón, Tuomo
2008
9 p. 2377-2386
10 p.
article
11 A method for rapid vulnerability assessment of structures loaded by outside blasts Cizelj, Leon
2009
9 p. 1641-1646
6 p.
article
12 A model based on bootstrapped neural networks for computing the maximum fuel cladding temperature in an Rmbk-1500 nuclear reactor accident Cadini, F.
2008
9 p. 2165-2172
8 p.
article
13 A modified equilibrium void distribution model applicable to subchannel-scale vapor–liquid cross flow model for conventional square and tight lattice BWR fuel bundles Hotta, Akitoshi
2005
9 p. 983-999
17 p.
article
14 Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm Cong, Tenglong
2011
9 p. 3945-3951
7 p.
article
15 Analysis of subcooled boiling flow with one-group interfacial area transport equation and bubble lift-off model Bae, Byoung-Uhn
2010
9 p. 2281-2294
14 p.
article
16 An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head Tran, C.T.
2010
9 p. 2148-2159
12 p.
article
17 An integrated expert system for optimum in core fuel management Elmoatty, Mona S. Abd
2011
9 p. 3707-3718
12 p.
article
18 Application of mechanistic criteria of cladding oxide shell failure to the analysis of core degradation simulated in bundle meltdown tests Veshchunov, M.S.
2008
9 p. 2219-2229
11 p.
article
19 A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application Huang, Yin-Nan
2011
9 p. 3985-3995
11 p.
article
20 A probabilistic seismic risk assessment procedure for nuclear power plants: (I) Methodology Huang, Yin-Nan
2011
9 p. 3996-4003
8 p.
article
21 A review on the clad failure studies Alam, Tanweer
2011
9 p. 3658-3677
20 p.
article
22 A scoping study of debris bed formation in the DEFOR test facility Karbojian, A.
2009
9 p. 1653-1659
7 p.
article
23 A second order turbulence model based on a Reynolds stress approach for two-phase boiling flow and application to fuel assembly analysis Mimouni, S.
2010
9 p. 2225-2232
8 p.
article
24 A second order turbulence model based on a Reynolds stress approach for two-phase boiling flow. Part 1: Application to the ASU-annular channel case Mimouni, S.
2010
9 p. 2233-2243
11 p.
article
25 A simple approach to the prediction of waterhammer transients in a pipe line with entrapped air Epstein, Michael
2008
9 p. 2182-2188
7 p.
article
26 A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1 Rýdl, Adolf
2008
9 p. 2387-2391
5 p.
article
27 A study on physicochemical properties of epoxy coating system for nuclear power plants Lee, Jae-Rock
2006
9 p. 931-937
7 p.
article
28 A study on the evolution of crack networks under thermal fatigue loading Kamaya, Masayuki
2008
9 p. 2147-2154
8 p.
article
29 A three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor Yamano, Hidemasa
2009
9 p. 1673-1681
9 p.
article
30 A two-phase methodology to predict FAC wear sites in the piping system of a BWR Ferng, Yuh Ming
2008
9 p. 2189-2196
8 p.
article
31 Basic research in support of innovative fuels design for the GEn IV systems: The F-BRIDGE project Valot, Carole
2011
9 p. 3521-3529
9 p.
article
32 Benchmark database on the evolution of two-phase flows in a vertical pipe Lucas, D.
2010
9 p. 2338-2346
9 p.
article
33 Buckling assessment procedure for large diameter vessel with multiple local thin areas subjected to external moment Mukaimachi, Norihiko
2011
9 p. 3632-3644
13 p.
article
34 BWR fuel cycle optimization using neural networks Ortiz-Servin, Juan José
2011
9 p. 3729-3735
7 p.
article
35 Calculation of heat capacity of the nuclear fuels UO2 and NpO2 using integer and non-integer n-dimensional Debye functions Koç, H.
2011
9 p. 3678-3682
5 p.
article
36 CFD analysis of a turbulent jet behavior induced by a steam jet discharge through a single hole in a subcooled water tank Kang, Hyung Seok
2010
9 p. 2160-2168
9 p.
article
37 CFD applications in the Pebble Bed Modular Reactor Project: A decade of progress Janse van Rensburg, J.J.
2011
9 p. 3683-3696
14 p.
article
38 CFD for subcooled flow boiling: Simulation of DEBORA experiments Krepper, Eckhard
2011
9 p. 3851-3866
16 p.
article
39 CFD methodology and validation for single-phase flow in PWR fuel assemblies Conner, Michael E.
2010
9 p. 2088-2095
8 p.
article
40 CFD-modeling of insulation debris transport phenomena in water flow Krepper, Eckhard
2010
9 p. 2357-2364
8 p.
article
41 CFD study on coolant mixing in VVER-440 fuel rod bundles and fuel assembly heads Tóth, S.
2010
9 p. 2194-2205
12 p.
article
42 Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus Yun, B.J.
2010
9 p. 2295-2303
9 p.
article
43 Characterization of radiation fields and dose assessment from fuels manufacturing for advanced fuel cycles Hawkins, Benjamin J.
2011
9 p. 3736-3747
12 p.
article
44 Check of the 2005-look up table for prediction of CHF in bundles Kolev, Nikolay Ivanov
2007
9 p. 978-981
4 p.
article
45 Comments on “Effect of uncertainties in best-estimate thermal hydraulic analysis on core damage frequency for PSA” Y.-J. Choa, T.-J. Kima, H.-G. Limb, G.-C. Parka Pourgol-Mohammad, Mohammad
2011
9 p. 4060-
1 p.
article
46 Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters Manera, A.
2009
9 p. 1718-1724
7 p.
article
47 Computational fluid dynamics simulation of a rectangular slit real impactor's performance Hari, Sridhar
2005
9 p. 1015-1028
14 p.
article
48 Contents 2010
9 p. iv-v
nvt p.
article
49 Contents 2009
9 p. iv-v
nvt p.
article
50 Contents 2011
9 p. v-viii
nvt p.
article
51 Corrigendum to “Novel porous media formulation for multiphase flow conservation equations” [Nucl. Eng. Des. 237 (2007) 918–942] Sha, W.T.
2008
9 p. 2494-
1 p.
article
52 Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system Kotlyar, D.
2011
9 p. 3777-3786
10 p.
article
53 Degradation of aged plants by corrosion: “Long cell action” in unresolved corrosion issues Saji, Genn
2009
9 p. 1591-1613
23 p.
article
54 Design of the advanced accumulator for the pressurized water reactor Shiraishi, Tadashi
2011
9 p. 3910-3924
15 p.
article
55 Determination of fatigue curve parameters at cyclic strain limited loading according to the mechanical characteristics of power energy structural materials Bražėnas, Algis
2011
9 p. 3596-3604
9 p.
article
56 Development of an in situ Raman spectroscopic system for surface oxide films on metals and alloys in high temperature water Kim, Ji Hyun
2005
9 p. 1029-1040
12 p.
article
57 Droplet de-entrainment by inertial impaction on vertical rods in an air-droplet mixture flow Lee, Kyung-Won
2006
9 p. 1003-1012
10 p.
article
58 2D simulation of the initiation and propagation of crack array under thermal fatigue Haddar, N.
2005
9 p. 945-964
20 p.
article
59 Effect of notch dimension on the fatigue life of V-notched structure Chang-zheng, Cheng
2011
9 p. 3573-3579
7 p.
article
60 Effects of dimensional change strain in nuclear graphite component stress analysis Tsang, D.K.L.
2007
9 p. 897-904
8 p.
article
61 Effects of mechanical vibration on critical heat flux in vertical annulus tube Kim, Dae Hun
2007
9 p. 982-987
6 p.
article
62 ENEN's approaches and initiatives for nuclear education and training Safieh, Joseph
2011
9 p. 3530-3539
10 p.
article
63 European Commission – 7th Framework Programme Fiorini, G.L.
2011
9 p. 3461-3469
9 p.
article
64 European lead fast reactor—ELSY Alemberti, Alessandro
2011
9 p. 3470-3480
11 p.
article
65 European Nuclear Conference Announcement 2007
9 p. 996-
1 p.
article
66 European supercritical water cooled reactor Schulenberg, T.
2011
9 p. 3505-3513
9 p.
article
67 Evolution in the design and development of the in-service inspection device for the Indian 500MWe Fast Breeder Reactor Singh, Ashutosh Pratap
2011
9 p. 3719-3728
10 p.
article
68 Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined space Zhao, D.W.
2008
9 p. 2460-2467
8 p.
article
69 Experimental CFD grade data for stratified two-phase flows Vallée, Christophe
2010
9 p. 2347-2356
10 p.
article
70 Experimental evaluation of the water ingression mechanism for corium cooling Lomperski, S.
2007
9 p. 905-917
13 p.
article
71 Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels Gang, Wu
2011
9 p. 4045-4054
10 p.
article
72 Experimental investigation of spray induced gas stratification break-up and mixing in two interconnected vessels Erkan, Nejdet
2011
9 p. 3935-3944
10 p.
article
73 Experimental studies and CFD calculations for buoyancy driven mixing phenomena da Silva, Marco Jose
2010
9 p. 2185-2193
9 p.
article
74 Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high-resolution measurement techniques and numerical modeling Kliem, S.
2010
9 p. 2271-2280
10 p.
article
75 Extending image processing strain measurement system to evaluate fracture behavior of wall-thinned pipes Tsuji, Masataka
2011
9 p. 3605-3612
8 p.
article
76 Failure analysis of the standby liquid control system for a boiling water reactor with fuzzy cognitive maps Núñez-Carrera, Alejandro
2011
9 p. 4004-4012
9 p.
article
77 Failure characteristics of cladding tubes under RIA conditions Leclercq, Sylvain
2008
9 p. 2206-2218
13 p.
article
78 Feedback reactivity coefficients and their coupling Khan, Rustam
2007
9 p. 972-977
6 p.
article
79 Finite element analysis of the optimized H type grid spring by using gap elements Kim, Kang Soo
2008
9 p. 2239-2244
6 p.
article
80 FISA-2009 Conference on Euratom Research and Training Activities: Nuclear Fission – Past, Present and Future (Generation-II, -III and -IV+Partitioning and Transmutation) Bhatnagar, V.
2011
9 p. 3376-3388
13 p.
article
81 Flow measurement techniques in heavy liquid metals Schulenberg, Thomas
2010
9 p. 2077-2087
11 p.
article
82 Fluent analysis of a ROSA cold leg stratification test Farkas, T.
2010
9 p. 2169-2175
7 p.
article
83 Fluid-structure interaction analysis of large-break loss of coolant accident Brandt, Tellervo
2010
9 p. 2365-2374
10 p.
article
84 Foreword Hugon, Michel
2011
9 p. 3375-
1 p.
article
85 Frontispiece 2010
9 p. iii-
1 p.
article
86 Frontispiece 2009
9 p. iii-
1 p.
article
87 Frontispiece 2011
9 p. iv-
1 p.
article
88 Functional reliability analysis of Safety Grade Decay Heat Removal System of Indian 500MWe PFBR Mathews, T. Sajith
2008
9 p. 2369-2376
8 p.
article
89 Fuzzy methodology applied to Probabilistic Safety Assessment for digital system in nuclear power plants Guimarães, Antonio César Ferreira
2011
9 p. 3967-3976
10 p.
article
90 Gas cooled fast reactor research in Europe Stainsby, Richard
2011
9 p. 3481-3489
9 p.
article
91 Heat transfer in two-component internal mist cooling Novak, V.
2008
9 p. 2341-2350
10 p.
article
92 Heat transfer in two-component internal mist cooling Novak, V.
2008
9 p. 2351-2358
8 p.
article
93 High and very high temperature reactor research for multipurpose energy applications Hittner, Dominique
2011
9 p. 3490-3504
15 p.
article
94 Homogenisation method for the dynamic analysis of a complete nuclear steam generator with fluid–structure interaction Sigrist, Jean-François
2008
9 p. 2261-2271
11 p.
article
95 Hydraulic study of turbulent flow in MTR-type nuclear fuel assembly Ha, Taesung
2006
9 p. 975-984
10 p.
article
96 Impact of partitioning and transmutation on the high level waste management González-Romero, E.M.
2011
9 p. 3436-3444
9 p.
article
97 Implementing risk-informed life-cycle design Hill III, Ralph S.
2009
9 p. 1699-1702
4 p.
article
98 Incipient fault detection of motor-operated valves using wavelet transform analysis Carneiro, Alvaro Luiz Guimarães
2008
9 p. 2453-2459
7 p.
article
99 Influence of pump starting times on transient flows in pipes Elaoud, Sami
2011
9 p. 3624-3631
8 p.
article
100 Innovative materials for Gen IV systems and transmutation facilities: The cross-cutting research project GETMAT Fazio, Concetta
2011
9 p. 3514-3520
7 p.
article
101 Insights from fire PSA for enhancing NPP safety Vinod, Gopika
2008
9 p. 2359-2368
10 p.
article
102 Integrated infrastructure initiatives for material testing reactor innovations Dekeyser, Jean
2011
9 p. 3540-3552
13 p.
article
103 Integrating Safety Critical Software System in Probabilistic Safety Assessment Vinod, Gopika
2008
9 p. 2392-2399
8 p.
article
104 Knowledge-directed characterization of nuclear power plant reactor core parameters West, Graeme M.
2011
9 p. 4013-4025
13 p.
article
105 Large eddy simulation of turbulent flow surrounding two simulated CANDU fuel bundles Zhang, X.
2011
9 p. 3553-3572
20 p.
article
106 Large-Eddy Simulation study of turbulent mixing in a T-junction Kuczaj, A.K.
2010
9 p. 2116-2122
7 p.
article
107 LEIS for the prediction of turbulent multifluid flows applied to thermal-hydraulics applications Lakehal, Djamel
2010
9 p. 2096-2106
11 p.
article
108 Limit load solutions of thick-walled cylinders with fully circumferential cracks under combined internal pressure and axial tension Gao, Zengliang
2008
9 p. 2155-2164
10 p.
article
109 Magnetohydrodynamic instability in annular linear induction pump Araseki, Hideo
2006
9 p. 965-974
10 p.
article
110 Meeting EU's energy needs through nuclear fission: Synergy of public and private research in an international context Bamberger, Yves
2011
9 p. 3445-3450
6 p.
article
111 Methods for the evaluation and synthesis of multiple sources of information applied to nuclear computer codes Destercke, S.
2008
9 p. 2484-2493
10 p.
article
112 Minimization of an initial fast reactor uranium–plutonium load by using enriched lead-208 as a coolant Khorasanov, G.L.
2009
9 p. 1703-1707
5 p.
article
113 Model extension and improvement for simulator-based software safety analysis Huang, Hui-Wen
2007
9 p. 955-971
17 p.
article
114 Modeling and measurement of interfacial area concentration in two-phase flow Paranjape, Sidharth
2010
9 p. 2329-2337
9 p.
article
115 Modeling free surface flows relevant to a PTS scenario: Comparison between experimental data and three RANS based CFD-codes. Comments on the CFD-experiment integration and best practice guideline Bartosiewicz, Yann
2010
9 p. 2375-2381
7 p.
article
116 Modeling pressure suppression pool hydrodynamics in the ABWR containment Sawant, Pravin
2011
9 p. 3824-3838
15 p.
article
117 Modelling of PWR lower head failure under severe accident loading using improved shells of revolution theory Koundy, Vincent
2008
9 p. 2400-2410
11 p.
article
118 Modelling of sprays in containment applications with A CMFD code Mimouni, S.
2010
9 p. 2260-2270
11 p.
article
119 900MW PWR containment mechanical behavior characteristics during containment test Zhang, Xuyao
2009
9 p. 1647-1652
6 p.
article
120 New capabilities of simulating fission product transport in circuits with ASTEC/SOPHAEROS v.1.3 Cousin, F.
2008
9 p. 2430-2438
9 p.
article
121 New explicit correlations for turbulent flow friction factor Brkić, Dejan
2011
9 p. 4055-4059
5 p.
article
122 Nondestructive measurement of the weight of kernels in a simulated cylindrical fuel compact for HTGR using X-ray computed tomography Kim, Woong Ki
2011
9 p. 3748-3752
5 p.
article
123 Nonlinear fluid–structure interaction calculation of the leakage behaviour of cracked concrete walls Niklasch, Christoph
2009
9 p. 1628-1640
13 p.
article
124 Non-linear response of reinforced concrete containment structure under blast loading Pandey, A.K.
2006
9 p. 993-1002
10 p.
article
125 Novel porous media formulation for multiphase flow conservation equations Sha, W.T.
2007
9 p. 918-942
25 p.
article
126 Nuclear and Radiological Emergency Management and Rehabilitation Strategies: Towards a EU approach for decision support tools Raskob, W.
2011
9 p. 3395-3402
8 p.
article
127 Nuclear magnetic resonance: A new tool for the validation of multiphase multidimensional CFD codes Lemonnier, H.
2010
9 p. 2139-2147
9 p.
article
128 Nuclear powered heat pumps for near-term process heat applications Marmier, A.
2008
9 p. 2272-2284
13 p.
article
129 Numerical modeling of crack propagation and shielding effects in a striping network Seyedi, Mohammad
2006
9 p. 954-964
11 p.
article
130 NURESIM – A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis Chauliac, Christian
2011
9 p. 3416-3426
11 p.
article
131 On various forms of the heat and mass transfer analogy: Discussion and application to condensation experiments Ambrosini, W.
2006
9 p. 1013-1027
15 p.
article
132 Optimized aspect ratios of restrained thick-wall cylinders by virtue of Poisson's ratio selection. Part two: Temperature application Whitty, J.P.M.
2011
9 p. 3587-3595
9 p.
article
133 Parametric analyses of partial sub-assembly blockages of the 50MWth gas cooled experimental technology and demonstrator reactor (ETDR) Carlsson, J.
2011
9 p. 3812-3823
12 p.
article
134 Parametric evaluation of large-scale high-temperature electrolysis hydrogen production using different advanced nuclear reactor heat sources Harvego, Edwin A.
2009
9 p. 1571-1580
10 p.
article
135 PARIS project: Radiolytic oxidation of molecular iodine in containment during a nuclear reactor severe accident: Part 2. Formation and destruction of iodine oxides compounds under irradiation – Experimental results modelling Bosland, L.
2011
9 p. 4026-4044
19 p.
article
136 Passive containment cooling system (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a postulated Loss of Coolant Accident (LOCA) Paladino, Domenico
2011
9 p. 3925-3934
10 p.
article
137 PATH – An experimental facility for natural circulation heat transfer studies related to Post Accident Thermal Hydraulics Gnanadhas, Lydia
2011
9 p. 3839-3850
12 p.
article
138 PERFORM 60: Prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling – 60 years foreseen plant lifetime Al Mazouzi, A.
2011
9 p. 3403-3415
13 p.
article
139 PIV measurements of turbulent jet and pool mixing produced by a steam jet discharge in a subcooled water pool Choo, Yeon Jun
2010
9 p. 2215-2224
10 p.
article
140 Plant life management and modernisation: Research challenges in the EU Rintamaa, R.
2011
9 p. 3389-3394
6 p.
article
141 Power peakings in mixed TRIGA cores Snoj, Luka
2008
9 p. 2473-2479
7 p.
article
142 Prediction of void fraction for PWR and BWR conditions with the sub-channel code F-COBRA-TF Gabriel, H.
2011
9 p. 3952-3966
15 p.
article
143 Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow Chenu, A.
2011
9 p. 3898-3909
12 p.
article
144 Pressure-tube and calandria-tube deformation following a single-channel blockage event in ACR-700 Gerardi, C.
2007
9 p. 943-954
12 p.
article
145 Primary loop study of a VVER-1000 reactor with special focus on coolant mixing Böttcher, Michael
2010
9 p. 2244-2253
10 p.
article
146 Probabilistic assessment of creep crack growth rate for Gr. 91 steel Kim, Woo-Gon
2011
9 p. 3580-3586
7 p.
article
147 Progress on PWR lower head failure predictive models Koundy, Vincent
2008
9 p. 2420-2429
10 p.
article
148 Prospective scenarios of nuclear energy evolution on the XXIst century over the world scale Massara, Simone
2009
9 p. 1708-1717
10 p.
article
149 Relation between the occurrence of Burnout and differential pressure fluctuation characteristics caused by the disturbance waves passing by a flow obstacle in a vertical boiling two-phase upward flow in a narrow annular channel Mori, Shoji
2006
9 p. 985-992
8 p.
article
150 RPV material investigations of the former VVER-440 Greifswald NPP Rindelhardt, Udo
2009
9 p. 1581-1590
10 p.
article
151 Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCA Bae, Byoung Uhn
2008
9 p. 2197-2205
9 p.
article
152 Scientific paradigms of structural safety of aged plants—Lessons learned from Russian activities Saji, Genn
2009
9 p. 1614-1627
14 p.
article
153 Sensitivity analysis of numerically determined linear stability boundaries of a supercritical heated channel T’Joen, C.
2011
9 p. 3879-3889
11 p.
article
154 Severe accident management strategy verification for VVER-1000 (V320) reactor Chatterjee, B.
2011
9 p. 3977-3984
8 p.
article
155 Shape optimization of a perforated pressure vessel cover under linearized stress constraints Choi, Woo-Seok
2008
9 p. 2468-2472
5 p.
article
156 Simulation of a gas jet entering the secondary side of a steam generator during a SGTR sequence: Validation of a FLUENT 6.2 Model Prá, C. López del
2010
9 p. 2206-2214
9 p.
article
157 Simulation of containment jet flows including condensation Heitsch, Matthias
2010
9 p. 2176-2184
9 p.
article
158 Simulation of turbulent and thermal mixing in T-junctions using URANS and scale-resolving turbulence models in ANSYS CFX Frank, Th.
2010
9 p. 2313-2328
16 p.
article
159 Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization Cao, Liangzhi
2008
9 p. 2292-2301
10 p.
article
160 Space reactor power systems with no single point failures El-Genk, Mohamed S.
2008
9 p. 2245-2255
11 p.
article
161 Steady-state RANS-simulations of the mixing in a T-junction Walker, C.
2010
9 p. 2107-2115
9 p.
article
162 Strengths and weakness of the methodologies for the innovative nuclear systems analysis Florido, Pablo C.
2007
9 p. 988-995
8 p.
article
163 Study of an optimization approach for a disposal tunnel layout, taking into account the geological environment with spatially heterogeneous characteristics Suyama, Yasuhiro
2009
9 p. 1693-1698
6 p.
article
164 Study of nitrogen injection to enhance forced convection for gas fast reactors Tauveron, N.
2011
9 p. 3787-3803
17 p.
article
165 Study of tearing behaviour of a PWR reactor pressure vessel lower head under severe accident loadings Koundy, Vincent
2008
9 p. 2411-2419
9 p.
article
166 Sustainable integration of EU research in severe accident phenomenology and management Van Dorsselaere, Jean-Pierre
2011
9 p. 3451-3460
10 p.
article
167 The experimental investigation of a crack's influence on the concrete breakout strength of a cast-in-place anchor Jang, J.B.
2006
9 p. 948-953
6 p.
article
168 The modeling of graphite oxidation behavior for HTGR fuel coolant channels under normal operating conditions Yu, Xinli
2008
9 p. 2230-2238
9 p.
article
169 Theoretical analysis of mass transfer and reaction in a porous medium applied to the gasification of graphite by water vapor Xiaowei, Luo
2006
9 p. 938-947
10 p.
article
170 Theoretical modeling of condensation of steam outside different vertical geometries (tube, flat plates) in the presence of noncondensable gases like air and helium Ganguli, Arijit
2008
9 p. 2328-2340
13 p.
article
171 The reactor physics characteristics of a transuranic mixed oxide fuel in a heavy water moderated reactor Morreale, A.C.
2011
9 p. 3768-3776
9 p.
article
172 Thermal-fluid characteristics of the transuranics fuel in a deep-burn HTR core Jun, Ji Su
2011
9 p. 3867-3878
12 p.
article
173 Thermal hydraulic effect of fuel plate surface roughness Guillen, Donna Post
2008
9 p. 2480-2483
4 p.
article
174 Thermal stress analysis of containment building in case of a Main Steam Line Break (MSLB) Thangamani, I.
2009
9 p. 1660-1672
13 p.
article
175 Topical issue on XCFD4NRS Smith, Brian L.
2010
9 p. 2075-2076
2 p.
article
176 Towards a multi-scale approach of two-phase flow modeling in the context of DNB modeling Jamet, D.
2010
9 p. 2131-2138
8 p.
article
177 Transient thermal stress intensity factors for Mode I edge-cracks Zhou, Zhen-huan
2011
9 p. 3613-3623
11 p.
article
178 Transmission probability method for solving neutron transport equation in three-dimensional triangular-z geometry Liu, Guoming
2008
9 p. 2285-2291
7 p.
article
179 Two-phase flow patterns in turbulent flow through a dose diffusion pipe Tang, H.
2005
9 p. 1001-1014
14 p.
article
180 Two types of a passive safety containment for a near future BWR with active and passive safety systems Sato, Takashi
2009
9 p. 1682-1692
11 p.
article
181 Ultra fast electron beam X-ray computed tomography for two-phase flow measurement Fischer, F.
2010
9 p. 2254-2259
6 p.
article
182 Uncertainties of creep model in stress analysis and life prediction of graphite component Wang, Haitao
2008
9 p. 2256-2260
5 p.
article
183 Uncertainty and sensitivity analyses as a validation tool for BWR bundle thermal–hydraulic predictions Hernandez-Solis, Augusto
2011
9 p. 3697-3706
10 p.
article
184 Validation of the sub-channel code F-COBRA-TF Glück, M.
2008
9 p. 2317-2327
11 p.
article
185 Validation of the sub-channel code F-COBRA-TF Glück, M.
2008
9 p. 2308-2316
9 p.
article
186 Verification and validation considerations regarding the qualification of numerical schemes for LES for dilution problems Ducros, F.
2010
9 p. 2123-2130
8 p.
article
187 Verification and validation of a CFD model for simulations of large-scale compartment fires Suard, S.
2011
9 p. 3645-3657
13 p.
article
188 Vibration-based diagnosis techniques used in nuclear power plants: An overview of experiences Sinha, Jyoti K.
2008
9 p. 2439-2452
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article
189 Wave propagation visualization in an experimental model for a control rod drive mechanism assembly Lee, Jung-Ryul
2011
9 p. 3761-3767
7 p.
article
                             189 results found
 
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