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 14 p. |
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 |