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                             153 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Academic validation of multi-phase flow codes Pigny, Sylvain L.

11 p. 3819-3829
artikel
2 A CFD method to evaluate the integrated influence of leakage and bypass flows on the PBMR Reactor Unit Janse van Rensburg, J.J.

11 p. 3841-3850
artikel
3 A comparative CFD investigation of helical wire-wrapped 7, 19 and 37 fuel pin bundles and its extendibility to 217 pin bundle Gajapathy, R.
2009
11 p. 2279-2292
14 p.
artikel
4 Address to the High Temperature Reactor Conference “HTR-2006” by Minister of Public Enterprises Erwin, Alec
2008
11 p. 2840-2841
2 p.
artikel
5 A finite element LES for high-Re flow in a short-elbow pipe with undisturbed inlet velocity Eguchi, Yuzuru
2011
11 p. 4368-4378
11 p.
artikel
6 Aging management of instrumentation & control sensors in nuclear power plants Hashemian, H.M.

11 p. 3781-3790
artikel
7 Analyses of a restrained growth graphite irradiation creep experiment Tsang, D.K.L.
2008
11 p. 3026-3030
5 p.
artikel
8 Analyses of operational transients in the TRADE experimental program Gabrielli, F.
2009
11 p. 2349-2356
8 p.
artikel
9 Analyses on fluid flow and heat transfer inside Calandria vessel of CANDU-6 using CFD Kim, Manwoong
2006
11 p. 1155-1164
10 p.
artikel
10 Analysis of startup oscillations in natural circulation boiling systems Lakshmanan, S.P.
2009
11 p. 2391-2398
8 p.
artikel
11 Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients Zerkak, Omar
2007
11 p. 1195-1208
14 p.
artikel
12 Analytical model for calculation of the thermo hydraulic parameters in a fuel rod assembly Cesna, B.

11 p. 3708-3715
artikel
13 Analytical model for time to cover cracking in RC structures due to rebar corrosion Bhargava, Kapilesh
2006
11 p. 1123-1139
17 p.
artikel
14 An approach to the construction of a one top fire event PSA model Kang, Dae Il
2009
11 p. 2514-2520
7 p.
artikel
15 A new method to derive one set of scaling criteria for reactor natural circulation at single and two-phase conditions Lu, Donghua

11 p. 3851-3861
artikel
16 Anomalies and other concerns related to the critical heat flux Groeneveld, D.C.
2011
11 p. 4604-4611
8 p.
artikel
17 An optimal loading principle of burnable poisons for an OTTO refueling scheme in pebble bed HTGR cores Tran, Hoai Nam
2009
11 p. 2357-2364
8 p.
artikel
18 A numerical investigation of three-dimensional flows in large volumes in the context of passive containment cooling in BWRs Smith, Brian L.
2007
11 p. 1175-1184
10 p.
artikel
19 A numerical procedure for computing the fragility of NPP components under random seismic excitation De Grandis, Silvia
2009
11 p. 2491-2499
9 p.
artikel
20 A numerical study of radiation heat transfer in sodium pool combustion and response surface modeling of luminous flame emissivity Yamaguchi, Akira
2006
11 p. 1179-1191
13 p.
artikel
21 A PANDA integral test on the effect of light gas on a Passive Containment Cooling System (PCCS) Paladino, Domenico
2011
11 p. 4551-4561
11 p.
artikel
22 A reinterpretation of measurements in developing annular two-phase flow Adamsson, Carl
2011
11 p. 4562-4567
6 p.
artikel
23 A study of acoustic wave damping in water-filled pipes with zero flow and turbulent flow Chatoorgoon, V.
2009
11 p. 2326-2332
7 p.
artikel
24 A study of the effect of flow maldistribution on heat transfer performance in evaporators Pacio, Julio C.

11 p. 3868-3877
artikel
25 A system analysis tool with a 2D gas turbine modeling for the load transients of HTGRS Kim, Ji Hwan
2009
11 p. 2459-2467
9 p.
artikel
26 A web-based nuclear simulator using RELAP5 and LabVIEW Kim, K.D.
2007
11 p. 1185-1194
10 p.
artikel
27 Benchmark calculations of pressurizer model for Maanshan nuclear power plant using TRACE code Cheng, Yi-Hsiang
2009
11 p. 2343-2348
6 p.
artikel
28 CATHARE-3: A new system code for thermal-hydraulics in the context of the NEPTUNE project Emonot, P.
2011
11 p. 4476-4481
6 p.
artikel
29 CATHARE 2 V2.5_2: A single version for various applications Geffraye, G.
2011
11 p. 4456-4463
8 p.
artikel
30 CFD analyses of liquid metal flow in sub-channels for Gen IV reactors Chandra, Laltu
2011
11 p. 4391-4403
13 p.
artikel
31 CFD in supercritical water-cooled nuclear reactor (SCWR) with horizontal tube bundles Shang, Zhi
2011
11 p. 4427-4433
7 p.
artikel
32 CFD investigation of vertical rod bundles of supercritical water-cooled nuclear reactor Shang, Zhi
2009
11 p. 2562-2572
11 p.
artikel
33 CFD modelling of polydispersed bubbly two-phase flow around an obstacle Krepper, Eckhard
2009
11 p. 2372-2381
10 p.
artikel
34 CFD modelling of wall steam condensation by a two-phase flow approach Mimouni, S.
2011
11 p. 4445-4455
11 p.
artikel
35 Characteristics of a different fuel cycle in a PBMR-400 for burning reactor grade plutonium Mulder, Eben
2008
11 p. 2893-2897
5 p.
artikel
36 Characteristics of test and maintenance human errors leading to unplanned reactor trips in nuclear power plants Kim, Jaewhan
2009
11 p. 2530-2536
7 p.
artikel
37 Combined evaluation of second order turbulence model and polydispersion model for two-phase boiling flow and application to fuel assembly analysis Mimouni, S.
2011
11 p. 4523-4536
14 p.
artikel
38 Conceptual evaluation of fluid–structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor Lo Frano, R.
2009
11 p. 2333-2342
10 p.
artikel
39 Consequences of delayed air ingress following a depressurization accident in a high temperature reactor Haque, H.
2008
11 p. 3041-3046
6 p.
artikel
40 Contents 2008
11 p. iv-v
nvt p.
artikel
41 Contents (prelim v-vi) 2011
11 p. iv-v
nvt p.
artikel
42 Corium crust strength measurements Lomperski, S.
2009
11 p. 2551-2561
11 p.
artikel
43 Correlation of flow accelerated corrosion rate with iron solubility Fujiwara, K.
2011
11 p. 4482-4486
5 p.
artikel
44 Corrosion-induced bond strength degradation in reinforced concrete—Analytical and empirical models Bhargava, Kapilesh
2007
11 p. 1140-1157
18 p.
artikel
45 Critical impact energies for scabbing and perforation of concrete target Li, Q.M.
2006
11 p. 1140-1148
9 p.
artikel
46 Decontamination of nuclear graphite Fachinger, Johannes
2008
11 p. 3086-3091
6 p.
artikel
47 Deposition of ZrC coats on UO2 particles using the chloride process Chernikov, Albert
2008
11 p. 2861-2865
5 p.
artikel
48 Design and analysis of a thermal core for a high performance light water reactor Schulenberg, T.
2011
11 p. 4420-4426
7 p.
artikel
49 Design and optimization of a multistage turbine for helium cooled reactor Van den Braembussche, R.A.
2008
11 p. 3136-3144
9 p.
artikel
50 Design and optimization of fuzzy-PID controller for the nuclear reactor power control Liu, Cheng
2009
11 p. 2311-2316
6 p.
artikel
51 Detailed evaluation of coolant injection into the reactor vessel with RCS depressurization for high pressure sequences Park, Rae-Joon
2009
11 p. 2484-2490
7 p.
artikel
52 Determination of BWR minimum steam cooling reactor water level and associated steam flow using MAAP4 code Chen, Jyh-Jun

11 p. 3791-3796
artikel
53 Development and application of the PBMR fission product release calculation model van der Merwe, J.J.
2008
11 p. 3092-3101
10 p.
artikel
54 Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRS Hossain, K.
2008
11 p. 2976-2984
9 p.
artikel
55 Development of an innovative neutron flux mapping system Cho, Byung-Hak
2006
11 p. 1201-1209
9 p.
artikel
56 Development of a real-time detection strategy for process monitoring during nuclear fuel reprocessing using the UREX+3a method Goddard, Braden

11 p. 3904-3909
artikel
57 Development of flow-induced vibration evaluation methodology for large-diameter piping with elbow in Japan sodium-cooled fast reactor Yamano, Hidemasa
2011
11 p. 4464-4475
12 p.
artikel
58 Development of HTGR-coated particle fuel technology in Korea Lee, Young-Woo
2008
11 p. 2842-2853
12 p.
artikel
59 Editorial 2008
11 p. 2839-
1 p.
artikel
60 Engineering design elements of a two-phase thermosyphon for the purpose of transferring NGNP thermal energy to a hydrogen plant Sabharwall, Piyush
2009
11 p. 2293-2301
9 p.
artikel
61 Estimation of ex-vessel steam explosion pressure loads Leskovar, Matjaž
2009
11 p. 2444-2458
15 p.
artikel
62 Evaluation of a detailed radiation heat transfer model in a high temperature reactor systems simulation model van Antwerpen, H.J.
2008
11 p. 2985-2994
10 p.
artikel
63 Evaluation of alternate power conversion unit designs for the GT-MHR Baxi, C.B.
2008
11 p. 2995-3001
7 p.
artikel
64 Evaluation of flow accelerated corrosion by coupled analysis of corrosion and flow dynamics. Relationship of oxide film thickness, hematite/magnetite ratio, ECP and wall thinning rate Uchida, Shunsuke
2011
11 p. 4585-4593
9 p.
artikel
65 Evaluation of operators’ mental workload of human–system interface automation in the advanced nuclear power plants Jou, Yung-Tsan
2009
11 p. 2537-2542
6 p.
artikel
66 Experimental and computational investigation of LBE–water interaction in LIFUS 5 facility Ciampichetti, A.
2009
11 p. 2468-2478
11 p.
artikel
67 Experimental and numerical investigations of three-dimensional turbulent flow of water surrounding a CANDU simulation fuel bundle structure inside a channel Abbasian, F.
2009
11 p. 2224-2235
12 p.
artikel
68 Experimental investigation on bubble characteristics entrained by surface vortex Ezure, Toshiki
2011
11 p. 4575-4584
10 p.
artikel
69 Experimental investigations on steady state natural circulation behavior of multiple parallel boiling channel system Vyas, H.P.

11 p. 3862-3867
artikel
70 Experimental results on the coolability of a debris bed with multidimensional cooling effects Rashid, M.
2011
11 p. 4537-4543
7 p.
artikel
71 Extension of the inhomogeneous MUSIG model for bubble condensation Lucas, D.
2011
11 p. 4359-4367
9 p.
artikel
72 Feasibility study of a microsystem to analyse radioactive solutions Janssens-Maenhout, G.
2007
11 p. 1209-1219
11 p.
artikel
73 Fission gas production in reactor fuels including the effects of ternary fission Hu, Jianwei

11 p. 3751-3757
artikel
74 Fitness for service evaluation of cracked divider plate bolt locking tabs for nuclear steam generators Yang, Songyan
2009
11 p. 2242-2264
23 p.
artikel
75 FLICA-OVAP: A new platform for core thermal–hydraulic studies Fillion, Philippe
2011
11 p. 4348-4358
11 p.
artikel
76 Flow visualization in a pebble bed reactor experiment using PIV and refractive index matching techniques Hassan, Yassin A.
2008
11 p. 3080-3085
6 p.
artikel
77 Fluid structure interaction between rods and a cross flow – Numerical approach Simoneau, Jan-patrice
2011
11 p. 4515-4522
8 p.
artikel
78 Foreword Ninokata, Hisashi
2011
11 p. 4347-
1 p.
artikel
79 Frontispiece 2008
11 p. iii-
1 p.
artikel
80 Frontispiece 2011
11 p. iii-
1 p.
artikel
81 Gap instability of laminar flows in eccentric annular channels Piot, Estelle
2011
11 p. 4615-4620
6 p.
artikel
82 HTR's role in process heat applications Kuhr, Reiner
2008
11 p. 3013-3017
5 p.
artikel
83 Improvement in understanding of natural circulation phenomena in water cooled nuclear power plants Choi, Jong-Ho
2011
11 p. 4504-4514
11 p.
artikel
84 Influence of elbow curvature on flow structure at elbow outlet under high Reynolds number condition Ono, A.
2011
11 p. 4409-4419
11 p.
artikel
85 Interpretation of fission-product transport behaviour in the Phébus FPT0 and FPT1 tests Kissane, M.P.
2006
11 p. 1210-1223
14 p.
artikel
86 Introducing and validating a new method for coupling neutronic and thermal-hydraulic calculations Zare, Nafiseh

11 p. 3727-3739
artikel
87 Introduction to the PBMR heat transfer test facility Rousseau, P.G.
2008
11 p. 3060-3072
13 p.
artikel
88 In-vessel melt pool coolibility test—Description and results of LIVE experiments Gaus-Liu, X.

11 p. 3898-3903
artikel
89 Irradiation testing of matrix material for spherical HTR-10 fuel elements Tang, Chunhe
2008
11 p. 2886-2892
7 p.
artikel
90 Kinetic study of the UO2/C interaction by high-temperature mass spectrometry Gossé, S.
2008
11 p. 2866-2876
11 p.
artikel
91 Latest achievements of CEA and AREVA NP on HTR fuel fabrication Charollais, François
2008
11 p. 2854-2860
7 p.
artikel
92 Level 1 probabilistic safety assessment to support the design of the CEA 2400MWth gas-cooled fast reactor Bassi, C.

11 p. 3758-3780
artikel
93 Matched refractive-index PIV visualization of complex flow structure in a three-dimentionally connected dual elbow Yuki, Kazuhisa
2011
11 p. 4544-4550
7 p.
artikel
94 Material selection for spallation neutron source windows Sordo, F.
2009
11 p. 2573-2580
8 p.
artikel
95 Methods to derive seismic fragility of NPP components: A summary Pisharady, Ajai S.

11 p. 3878-3887
artikel
96 Microscopic thermal characterization of HTR particle layers Rochais, D.
2008
11 p. 3047-3059
13 p.
artikel
97 Modeling approaches for strongly non-homogeneous two-phase flows Morel, C.
2007
11 p. 1107-1127
21 p.
artikel
98 Modelling of the HFR-EU1BIS experiment and thermomechanical evaluation de Groot, S.
2008
11 p. 3114-3120
7 p.
artikel
99 Model of particle resuspension in turbulent flows Stempniewicz, M.M.
2008
11 p. 2943-2959
17 p.
artikel
100 New gas concentration measurement system for the PANDA containment test facility Ritterath, Martin
2011
11 p. 4594-4603
10 p.
artikel
101 Numerical effects of the semi-conservative form of momentum equations for multi-dimensional two-phase flows Park, I.K.
2009
11 p. 2365-2371
7 p.
artikel
102 Numerical investigation on bubble dynamics during flow boiling using moving particle semi-implicit method Chen, Ronghua

11 p. 3830-3840
artikel
103 Numerical simulation and experimental study on Resonant Acoustic Chambers—For novel, high-efficiency nuclear particle detectors Wang, Jing

11 p. 3716-3726
artikel
104 Numerical simulation of secondary flow in bubbly turbulent flow in sub-channel Ikeno, Tsutomu
2011
11 p. 4568-4574
7 p.
artikel
105 Numerical simulation on void bubble dynamics using moving particle semi-implicit method Tian, Wenxi
2009
11 p. 2382-2390
9 p.
artikel
106 On the analogies in the dynamic behaviour of heated channels with boiling and supercritical fluids Ambrosini, Walter
2007
11 p. 1164-1174
11 p.
artikel
107 Optimum RCS depressurization strategy for effective severe accident management of station black out accident Huh, Changwook
2009
11 p. 2521-2529
9 p.
artikel
108 Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR Hinssen, Hans-Klemens
2008
11 p. 3018-3025
8 p.
artikel
109 Plant control to avoid surge development in the case of a pipe rupture in a direct cycle HTGR Tauveron, Nicolas
2008
11 p. 2925-2934
10 p.
artikel
110 Probabilistic seismic hazard analysis for a site Ghosh, A.K.
2006
11 p. 1192-1200
9 p.
artikel
111 Promising designs of compact heat exchangers for modular HTRs using the Brayton cycle Pra, Franck
2008
11 p. 3160-3173
14 p.
artikel
112 Proper orthogonal decomposition of the flow in a tight lattice rod-bundle Merzari, E.
2011
11 p. 4621-4632
12 p.
artikel
113 Pu-breeding feasibility in PWR Delbeke, J.F.A.
2007
11 p. 1158-1163
6 p.
artikel
114 Radial variation in porosity in annular packed beds du Toit, C.G.
2008
11 p. 3073-3079
7 p.
artikel
115 RANS modeling for flow in nuclear fuel bundle in pressurized water reactors (PWR) Gandhir, A.
2011
11 p. 4404-4408
5 p.
artikel
116 Rate of droplet deposition in steam–water annular flow and effect of a flow obstacle Okawa, Tomio
2011
11 p. 4497-4503
7 p.
artikel
117 Reflux condensation of flowing vapor and non-condensable gases counter-current to laminar liquid film in a vertical tube Liao, Y.
2009
11 p. 2409-2416
8 p.
artikel
118 RELAP5 simulation of surge line break accident using combined and best estimate plus uncertainty approaches Krištof, Marián
2009
11 p. 2500-2513
14 p.
artikel
119 Reprint of: Rod bundle vortex networks, gap vortex streets, and gap instability: A nomenclature and some comments on available methodologies Tavoularis, Stavros
2011
11 p. 4612-4614
3 p.
artikel
120 Research on operational characteristics of passive residual heat removal system under rolling motion Yan, Bing-huo
2009
11 p. 2302-2310
9 p.
artikel
121 Results of AVR fuel pebble irradiation at increased temperature and burn-up in the HFR Petten Fütterer, Michael A.
2008
11 p. 2877-2885
9 p.
artikel
122 Revisiting large break LOCA with the CATHARE-3 three-field model Valette, Michel
2011
11 p. 4487-4496
10 p.
artikel
123 Revisiting the resolution requirements for turbulence simulations in nuclear heat transfer Grötzbach, G.
2011
11 p. 4379-4390
12 p.
artikel
124 Seismic proof test of a reinforced concrete containment vessel (RCCV) Hirama, Toshihiko
2007
11 p. 1128-1139
12 p.
artikel
125 Sensitivity studies of air ingress accidents in modular HTGRs Ball, Syd
2008
11 p. 2935-2942
8 p.
artikel
126 SiC encapsulation of (V)HTR components and waste by laser beam joining of ceramics Knorr, J.
2008
11 p. 3129-3135
7 p.
artikel
127 Single-phase CFD applicability for estimating fluid hot-spot locations in a 5×5 fuel rod bundle Ikeda, Kazuo
2006
11 p. 1149-1154
6 p.
artikel
128 Source term evaluation for the upgraded LEU Pakistan Research Reactor-1 under severe accidents Ullah, Sana

11 p. 3740-3750
artikel
129 South Africa's opportunity to maximise the role of nuclear power in a global hydrogen economy Greyvenstein, R.
2008
11 p. 3031-3040
10 p.
artikel
130 Steady state and transient temperature profiles in a multishell spherical system heated internally by reactor-grade plutonium Kessler, G.
2009
11 p. 2430-2443
14 p.
artikel
131 Structural evaluation of a piping system subjected to thermal stratification Chattopadhyay, Somnath
2009
11 p. 2236-2241
6 p.
artikel
132 Structure and mechanical properties of pyrolytic carbon produced by fluidized bed chemical vapor deposition López-Honorato, E.
2008
11 p. 3121-3128
8 p.
artikel
133 Study on mitigation of in-vessel release of fission products in severe accidents of PWR Huang, G.F.

11 p. 3888-3897
artikel
134 Study on the characteristic points of boiling curve by using wavelet analysis and genetic neural network Wei, H.M.
2009
11 p. 2317-2325
9 p.
artikel
135 The analytic nodal method in cylindrical geometry Prinsloo, Rian H.
2008
11 p. 2898-2907
10 p.
artikel
136 The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario King, Wayne E.

11 p. 3699-3707
artikel
137 The discrete equation method (DEM) for fully compressible, two-phase flows in ducts of spatially varying cross-section Berry, Ray A.

11 p. 3797-3818
artikel
138 The Operator Training Simulator System for the Pebble Bed Modular Reactor (PBMR) Plant Dudley, Trevor
2008
11 p. 2908-2915
8 p.
artikel
139 Theory of recovery of deuterium from water–isotopes mixture in spiral wired thermal diffusion columns of the Frazier scheme Yeh, Ho-Ming
2009
11 p. 2265-2271
7 p.
artikel
140 The Reactor Core Neutronic model for the Pebble Bed Modular Reactor Dudley, Trevor
2008
11 p. 3002-3012
11 p.
artikel
141 Thermal aging effect on Z3CN20.09M Cast Duplex Stainless Steel Xue, Fei
2009
11 p. 2217-2223
7 p.
artikel
142 Thermal hydraulic investigations of primary coolant pipe rupture in an LMFBR Natesan, K.
2006
11 p. 1165-1178
14 p.
artikel
143 Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations Kim, In Hun
2009
11 p. 2399-2408
10 p.
artikel
144 The Thermal–Hydraulic model for the pebble bed modular reactor (PBMR) plant operator training simulator system Dudley, Trevor
2008
11 p. 3102-3113
12 p.
artikel
145 TINTE analysis of PBMR reactivity insertion transients Sikik, Ugur Emre
2008
11 p. 2916-2924
9 p.
artikel
146 TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions Chenu, A.
2009
11 p. 2417-2429
13 p.
artikel
147 Trajectory-tracking control of underwater inspection robot for nuclear reactor internals using Time Delay Control Park, Joon-Young
2009
11 p. 2543-2550
8 p.
artikel
148 Transient analysis of Ghana Research Reactor-1 using PARET/ANL thermal–hydraulic code Ampomah-Amoako, E.
2009
11 p. 2479-2483
5 p.
artikel
149 Twisted-tape-induced swirl flow heat transfer and pressure drop in a short circular tube under velocities controlled Hata, K.
2011
11 p. 4434-4444
11 p.
artikel
150 Validation of the CATHARE2 code against experimental data from Brayton-cycle plants Bentivoglio, Fabrice
2008
11 p. 3145-3159
15 p.
artikel
151 Visualization of the ultrasound-induced behaviour of gas pockets entrapped on a patterned surface. Application to inspection of sodium-cooled fast reactors Paumel, K.
2009
11 p. 2272-2278
7 p.
artikel
152 Wall function approach for boiling two-phase flows Končar, Boštjan

11 p. 3910-3918
artikel
153 Xenon-induced axial power oscillations in the 400MW PBMR Strydom, Gerhard
2008
11 p. 2960-2975
16 p.
artikel
                             153 gevonden resultaten
 
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