Digitale Bibliotheek
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                             155 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR Haste, T.J.
2010
6 p. 1599-1605
7 p.
artikel
2 A conceptual design study of proliferation-resistant PWR fuel using reprocessed uranium Yamamoto, Akio
2005
6 p. 649-660
12 p.
artikel
3 Adaptive fuzzy model based predictive control of nuclear steam generators Eliasi, H.
2007
6 p. 668-676
9 p.
artikel
4 Advanced DVI for ECC direct bypass mitigation Kwon, Tae-Soon
2009
6 p. 1095-1102
8 p.
artikel
5 A hydrodynamical analysis for reactor primary containment by energy absorption Sorensen, H.C.
1968
6 p. 547-577
31 p.
artikel
6 An adaptive finite element approach for neutron transport equation Abbassi, M.
2011
6 p. 2143-2154
12 p.
artikel
7 An advanced method for determination of loss of coolant accident in nuclear power plants Mahmoodi, R.
2011
6 p. 2013-2019
7 p.
artikel
8 Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code Nikitin, Konstantin
2011
6 p. 2240-2247
8 p.
artikel
9 Analysis of drag and lift coefficient expressions of bubbly flow system for low to medium Reynolds number Pang, Ming Jun
2011
6 p. 2204-2213
10 p.
artikel
10 Analysis of fuel rod behavior under normal operating conditions in Super Fast Reactor Ju, Haitao
2010
6 p. 1450-1457
8 p.
artikel
11 Analysis of the IAEA research reactor benchmark problem by the RETRAC-PC code Bousbia-Salah, Anis
2005
6 p. 661-674
14 p.
artikel
12 Analysis of thermo–hydro–mechanical process in the engineered barrier system of a high-level waste repository Cho, Won-Jin
2010
6 p. 1688-1698
11 p.
artikel
13 Analytical solution to solve the point reactor kinetics equations Nahla, Abdallah A.
2010
6 p. 1622-1629
8 p.
artikel
14 An efficient iterative method for the general static thermoelastic sphere problem Holy, Z.J.
1968
6 p. 503-516
14 p.
artikel
15 An experimental investigation on bending stiffness and neutral axis depth variation of over-reinforced high strength concrete beams Mohammadhassani, Mohammad
2011
6 p. 2060-2067
8 p.
artikel
16 An experimental investigation on the quenching of a hot vertical heater by water injection at high flow rate Sahu, S.K.
2010
6 p. 1558-1568
11 p.
artikel
17 An improved interface model for molten corium–concrete interaction Guillaumé, Mathieu
2009
6 p. 1084-1094
11 p.
artikel
18 Application of a neural network based feedwater controller to helical steam generators Shen, Hengliang
2009
6 p. 1056-1065
10 p.
artikel
19 Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development Abánades, A.
2011
6 p. 2288-2294
7 p.
artikel
20 A study on the effects of ESFAS STI modification on the unavailability of ESF actuated components Lee, Yoon-Hwan
2011
6 p. 2224-2233
10 p.
artikel
21 Author index 1968
6 p. 586-587
2 p.
artikel
22 Author's closure on: ‘on the existence of the saint-venant solution of bending a prismatical beam containing longitudinal cavities’ by T. Leko Leko, T.
1968
6 p. 585-
1 p.
artikel
23 Behavior of zirconium fuel cladding under fast pressurization rates Kim, Jun Hwan
2008
6 p. 1441-1447
7 p.
artikel
24 Benchmark results for the “BWR-PB” fuel assembly based on pebble-bed coated particles with uranium dioxide and gadolinia poison Benchrif, Abdelfettah
2009
6 p. 1148-1154
7 p.
artikel
25 Buckling sensitivity analysis of cracked thin plates under membrane tension or compression loading Brighenti, Roberto
2009
6 p. 965-980
16 p.
artikel
26 Burn up calculations for the Iranian miniature reactor: A reliable and safe research reactor Faghihi, F.
2009
6 p. 1000-1009
10 p.
artikel
27 Characterization of crystallisation processes with electrical impedance spectroscopy Zhao, Yanlin
2011
6 p. 1938-1944
7 p.
artikel
28 Comparison of natural convection flows under VHTR type conditions modeled by both the conservation and incompressible forms of the Navier–Stokes equations Martineau, Richard C.
2010
6 p. 1371-1385
15 p.
artikel
29 Comparison of several resuspension models against measured data Stempniewicz, M.M.
2010
6 p. 1657-1670
14 p.
artikel
30 Computational study of conjugate heat transfer in T-junctions Kuhn, Simon
2010
6 p. 1548-1557
10 p.
artikel
31 Conceptual core design of Advanced Recycling Reactor based on mature technologies Ikeda, Kazumi
2011
6 p. 2318-2328
11 p.
artikel
32 Conditional release of materials from decommissioning process into the environment in the form of steel railway tracks Tatranský, Peter
2009
6 p. 1155-1161
7 p.
artikel
33 Consideration of uncertainties in seismic analysis of non-classically damped coupled systems Tadinada, Sashi Kanth
2011
6 p. 2034-2044
11 p.
artikel
34 Contents (prelim v-vi) 2011
6 p. iii-v
nvt p.
artikel
35 Core analysis at Paks NPP with a new generation of VERONA Végh, J.
2008
6 p. 1316-1331
16 p.
artikel
36 Core model of new German neutron source FRM II Röhrmoser, A.
2010
6 p. 1417-1432
16 p.
artikel
37 Critical strains and necking phenomena for different steel sheet specimens under uniaxial loading Jeschke, J.
2011
6 p. 2045-2052
8 p.
artikel
38 Design of transition cores of RSG GAS (MPR-30) with higher loading silicide fuel Liem, Peng Hong
2010
6 p. 1433-1442
10 p.
artikel
39 Determination of rupture frequency for feeders subject to flow accelerated corrosion Wang, Min
2011
6 p. 2234-2239
6 p.
artikel
40 Determination of the distribution of air and water in porous media by electrical impedance tomography and magneto-electrical imaging Haegel, Franz-Hubert
2011
6 p. 1959-1969
11 p.
artikel
41 Development and diversity and defense-in-depth application of ABWR feedwater pump and controller model Huang, Hui-Wen
2009
6 p. 1136-1147
12 p.
artikel
42 Development of a fouling monitor for safety-related heat exchangers Heo, Gyunyoung
2008
6 p. 1295-1303
9 p.
artikel
43 Development of a thermal–hydraulic system code for simulators based on RELAP5 code Lin, Meng
2005
6 p. 675-686
12 p.
artikel
44 Development of probabilistic models to estimate fire-induced cable damage at nuclear power plants Valbuena, Genebelin
2009
6 p. 1113-1127
15 p.
artikel
45 Development of the methods to change the fault tree logic structure according to the changing conditions of a system in a one top PSA model Yang, Joon-Eon
2008
6 p. 1400-1409
10 p.
artikel
46 Droplet entrainment correlation in vertical upward co-current annular two-phase flow Sawant, Pravin
2008
6 p. 1342-1352
11 p.
artikel
47 Effect of gamma and lead as an additive material on the resistance and strength of concrete Rezaei Ochbelagh, D.
2011
6 p. 2359-2363
5 p.
artikel
48 Effect of local wall thinning on the collapse behavior of pipe elbows subjected to a combined internal pressure and in-plane bending load Kim, Jin-Weon
2008
6 p. 1275-1285
11 p.
artikel
49 Effect of prestress force on longitudinal vibration of bonded tendons embedded in a nuclear containment Kim, Byeong Hwa
2010
6 p. 1281-1289
9 p.
artikel
50 Elemental analysis of cement used for radiation shielding by instrumental neutron activation analysis Medhat, M.E.
2011
6 p. 2138-2142
5 p.
artikel
51 European new build and fuel cycles in the 21st century Roelofs, Ferry
2011
6 p. 2307-2317
11 p.
artikel
52 Evaluation of the conduction shape factor with a CFD code for a liquid–metal heat transfer in heated triangular rod bundles Jeong, Hae-yong
2007
6 p. 648-654
7 p.
artikel
53 Experimental and computational investigation of a natural circulation system in Regional Energy Reactor-10MWth Jang, Byeong-Il
2011
6 p. 2214-2223
10 p.
artikel
54 Experimental and theoretical investigation of gas–liquid flow pressure drop across rupture discs Shannak, Benbella
2010
6 p. 1458-1467
10 p.
artikel
55 Experimental and theoretical study of the gas–water two phase flow through a conductance multiphase Venturi meter in vertical annular (wet gas) flow Hasan, Abbas H.A.M.
2011
6 p. 1998-2005
8 p.
artikel
56 Experimental investigation on ductile stable crack growth emanating from wire-cut notch in AISI 4340 steel Mourad, A.H.I.
2005
6 p. 637-647
11 p.
artikel
57 Experimental study on the vibrations of various fuel rod models in parallel flow Basile, D.
1968
6 p. 517-534
18 p.
artikel
58 Fast neutron fluence calculations as support for a BWR pressure vessel and internals surveillance program Lucatero, Marco A.
2010
6 p. 1271-1280
10 p.
artikel
59 Fatigue design of nuclear class 1 piping considering thermal stratification Kweon, Hyeong Do
2008
6 p. 1265-1274
10 p.
artikel
60 Fluid-structure interaction analysis of a hypothetical core disruptive accident in LMFBRs Liu, Chuang
2005
6 p. 701-712
12 p.
artikel
61 Free vibration of orthotropic super-elliptical plates on intermediate supports Altekin, M.
2009
6 p. 981-999
19 p.
artikel
62 From discovery to recognition of periodic large scale vortices in rod bundles as source of natural mixing between subchannels—A review Meyer, Leonhard
2010
6 p. 1575-1588
14 p.
artikel
63 Generalized flow pattern image reconstruction algorithm for electrical capacitance tomography Liu, S.
2011
6 p. 1970-1980
11 p.
artikel
64 Group theory transformation for Soret and Dufour effects on free convective heat and mass transfer with thermophoresis and chemical reaction over a porous stretching surface in the presence of heat source/sink Kandasamy, R.
2011
6 p. 2155-2161
7 p.
artikel
65 High temperature design curves for high nitrogen grades of 316LN stainless steel Ganesh Kumar, J.
2010
6 p. 1363-1370
8 p.
artikel
66 High temperature strength and inelastic behavior of plate–fin structures for HTGR Kawashima, F.
2007
6 p. 591-599
9 p.
artikel
67 Image reconstruction in electrostatic tomography using a priori knowledge from ECT Zhou, Bin
2011
6 p. 1952-1958
7 p.
artikel
68 Improvement of the seismic safety of existing nuclear power plants by an increase of the component seismic capacity: A case study Choun, Young-Sun
2008
6 p. 1410-1420
11 p.
artikel
69 Improvements in a CFD code for analysis of hydrogen behaviour within containments Martín-Valdepeñas, J.M.
2007
6 p. 627-647
21 p.
artikel
70 Improving SFR economics through innovations from thermal design and analysis aspects Zhao, Haihua
2009
6 p. 1042-1055
14 p.
artikel
71 Influence of axial power distribution on dryout: Film-flow models and experiments Adamsson, Carl
2010
6 p. 1495-1505
11 p.
artikel
72 INPRO economic assessment of the IRIS nuclear reactor for deployment in Brazil Gonçalves Filho, Orlando João Agostinho
2011
6 p. 2329-2338
10 p.
artikel
73 Intensely irradiated steel components: Plastic and fracture properties, and a new concept of structural design criteria for assuring the structural integrity Suzuki, Kazuhiko
2010
6 p. 1290-1305
16 p.
artikel
74 Iris small break loca phenomena identification and ranking table (PIRT) Larson, T.K.
2007
6 p. 618-626
9 p.
artikel
75 Large Eddy Simulation and the effect of the turbulent inlet conditions in the mixing Tee Ndombo, Jean-Marc
2011
6 p. 2172-2183
12 p.
artikel
76 Location and sizing of a plant stack: Design study using CFD Petrangeli, Gianni
2011
6 p. 2248-2256
9 p.
artikel
77 Long operation life reactor for lunar surface power El-Genk, Mohamed S.
2011
6 p. 2339-2352
14 p.
artikel
78 MARGARET: A comprehensive code for the description of fission gas behavior Noirot, L.
2011
6 p. 2099-2118
20 p.
artikel
79 Measurement of plastic strain of polycrystalline material by electron backscatter diffraction Kamaya, Masayuki
2005
6 p. 713-725
13 p.
artikel
80 Mechanical design issues and resolutions of a dual cooled fuel for the OPR-1000 Kim, Hyung-Kyu
2011
6 p. 2119-2127
9 p.
artikel
81 Methodology for a numerical simulation of an insertion or a drop of the rod cluster control assembly in a PWR Andriambololona, H.
2007
6 p. 600-606
7 p.
artikel
82 Model development for the estimation of fission product release under normal and accident conditions in a HTGR Jeong, Hyedong
2009
6 p. 1066-1075
10 p.
artikel
83 Modeling and optimization of a nuclear power plant secondary loop Teyssedou, A.
2010
6 p. 1403-1416
14 p.
artikel
84 Molten salt reactors: A new beginning for an old idea LeBlanc, David
2010
6 p. 1644-1656
13 p.
artikel
85 Multi-dimensional advances for industrial process monitoring Hammond, Robert B.
2011
6 p. 1937-
1 p.
artikel
86 Multidimensional effects in laminar filmwise condensation of water vapour in binary and ternary mixtures with noncondensable gases Karkoszka, Krzysztof
2008
6 p. 1373-1381
9 p.
artikel
87 Multi-pin modelling of PWR fuel pin ballooning during post-LOCA reflood Ammirabile, L.
2008
6 p. 1448-1458
11 p.
artikel
88 Multiple aspects of raw data collection and processing for Romanian TRIGA SSR Mladin, Daniela
2010
6 p. 1630-1643
14 p.
artikel
89 Noble gas binary mixtures for gas-cooled reactor power plants El-Genk, Mohamed S.
2008
6 p. 1353-1372
20 p.
artikel
90 Numerical assessment of pyrochemical process performance for PEACER system Bae, Judong
2010
6 p. 1679-1687
9 p.
artikel
91 Numerical computation of fragility curves for NPP equipment Zentner, I.
2010
6 p. 1614-1621
8 p.
artikel
92 Numerical simulation of turbulent flow in a 37-rod bundle Chang, D.
2007
6 p. 575-590
16 p.
artikel
93 Numerical study on flow field in inlet plenum of a pebble-bed modular reactor Ahmad, Imteyaz
2007
6 p. 565-574
10 p.
artikel
94 Online integrated visual inspection and sorting system for fast reactor fuels Mukherjee, D.
2010
6 p. 1392-1396
5 p.
artikel
95 On the speed of response of an FPGA-based shutdown system in CANDU nuclear power plants She, Jingke
2011
6 p. 2280-2287
8 p.
artikel
96 On the stability of the point reactor kinetics equations Theler, Germán G.
2010
6 p. 1443-1449
7 p.
artikel
97 Optimization of multi-layered metallic shield Ben-Dor, G.
2011
6 p. 2020-2025
6 p.
artikel
98 Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealing Rogers, Timothy
2009
6 p. 1019-1029
11 p.
artikel
99 Passive system reliability analysis using Response Conditioning Method with an application to failure frequency estimation of Decay Heat Removal of PFBR Sajith Mathews, T.
2011
6 p. 2257-2270
14 p.
artikel
100 Passive system reliability analysis using the APSRA methodology Nayak, A.K.
2008
6 p. 1430-1440
11 p.
artikel
101 Performance evaluation of PFBR wire type sodium leak detectors Vijayakumar, G.
2011
6 p. 2271-2279
9 p.
artikel
102 Performance of TRISO particles fueled with plutonium and minor actinides in a PBMR-400 core design Jonnet, J.
2010
6 p. 1320-1331
12 p.
artikel
103 Physico-chemical characterization of clays at Kalpakkam nuclear plant site towards assessment of radioactive waste disposal Deepthi Rani, R.
2011
6 p. 2353-2358
6 p.
artikel
104 Post-test analysis of helium circulator trip without scram at 3MW power level on the HTR-10 Chen, F.
2009
6 p. 1010-1018
9 p.
artikel
105 Potential improvements of supercritical recompression CO2 Brayton cycle by mixing other gases for power conversion system of a SFR Jeong, Woo Seok
2011
6 p. 2128-2137
10 p.
artikel
106 Potential steam generator tube rupture in the presence of severe accident thermal challenge and tube flaws due to foreign object wear Liao, Y.
2009
6 p. 1128-1135
8 p.
artikel
107 Predicting the preferential sites to liquid droplet erosion of the bellows assemblies by CFD Hu, H.X.
2011
6 p. 2295-2306
12 p.
artikel
108 Prediction of the obstacle effect on film-boiling heat transfer Leung, L.K.H.
2005
6 p. 687-700
14 p.
artikel
109 Preliminary seismic analysis of an innovative near term reactor: Methodology and application Lo Frano, R.
2010
6 p. 1671-1678
8 p.
artikel
110 Preliminary steps toward assessing aerosol retention in the break stage of a dry steam generator during severe accident SGTR sequences Herranz, L.E.
2008
6 p. 1392-1399
8 p.
artikel
111 Probabilistic characterization of AHWR Inner Containment using High Dimensional Model Representation Rao, B.N.
2009
6 p. 1030-1041
12 p.
artikel
112 Probabilistic seismic risk analysis of CANDU containment structure for near-fault earthquakes Choi, In-Kil
2008
6 p. 1382-1391
10 p.
artikel
113 Properties of DU–10wt% Mo alloys subjected to various post-rolling heat treatments Burkes, Douglas E.
2010
6 p. 1332-1339
8 p.
artikel
114 Quantification of unavailability caused by random failures and maintenance human errors in nuclear power plants Khalaquzzaman, M.
2010
6 p. 1606-1613
8 p.
artikel
115 Radiation-induced ‘long-cell’ (macro-cell) corrosion in light water reactors Saji, Genn
2010
6 p. 1340-1354
15 p.
artikel
116 Reactor cooling systems thermal–hydraulic assessment of the ASTEC V1.3 code in support of the French IRSN PSA-2 on the 1300MWe PWRs Tregoures, Nicolas
2010
6 p. 1468-1486
19 p.
artikel
117 Review and proposal for heat transfer predictions at supercritical water conditions using existing correlations and experiments Jäger, Wadim
2011
6 p. 2184-2203
20 p.
artikel
118 Scaling group transformation for MHD boundary-layer flow of a nanofluid past a vertical stretching surface in the presence of suction/injection Kandasamy, R.
2011
6 p. 2053-2059
7 p.
artikel
119 Seismic re-evaluation of EDF Bugey 900 PWR nuclear power plant in the frame of the 3rd periodic safety review Viallet, E.
2010
6 p. 1306-1319
14 p.
artikel
120 Shape optimization of wire-wrapped fuel assembly using Kriging metamodeling technique Raza, Wasim
2008
6 p. 1332-1341
10 p.
artikel
121 Simulation of basic gas mixing tests with condensation in the PANDA facility using the GOTHIC code Andreani, Michele
2010
6 p. 1528-1547
20 p.
artikel
122 Simulation of gas mixing and transport in a multi-compartment geometry using the GOTHIC containment code and relatively coarse meshes Andreani, Michele
2010
6 p. 1506-1527
22 p.
artikel
123 Spatial resolution analysis for real time applications in electrical capacitance tomography Neumayer, M.
2011
6 p. 1988-1993
6 p.
artikel
124 Spent fuel transport cask thermal evaluation under normal and accident conditions Pugliese, G.
2010
6 p. 1699-1706
8 p.
artikel
125 Sprays in containment: Final results of the SARNET spray benchmark Malet, J.
2011
6 p. 2162-2171
10 p.
artikel
126 Stability analysis of SiO2/SiC coatings on matrix graphite for HTR-10 fuel elements Fu, Zhi-qiang
2011
6 p. 2068-2074
7 p.
artikel
127 Static and dynamic hydroelastic instabilities in MTR-type fuel elements Part I. introduction and experimental investigation Smissaert, Georges E.
1968
6 p. 535-546
12 p.
artikel
128 Study of startup transients and power ramping of natural circulation boiling systems Lakshmanan, S.P.
2009
6 p. 1076-1083
8 p.
artikel
129 Study on modal characteristics of perforated shell using effective Young's modulus Jhung, Myung Jo
2011
6 p. 2026-2033
8 p.
artikel
130 Sub-channel analysis with F-COBRA-TF–Code validation and approaches to CHF prediction Glück, M.
2007
6 p. 655-667
13 p.
artikel
131 Subject index 1968
6 p. 588-590
3 p.
artikel
132 Survey of dust production in pebble bed reactor cores Cogliati, Joshua J.
2011
6 p. 2364-2369
6 p.
artikel
133 The effect of fuel rod supporting conditions on fuel rod vibration characteristics and grid-to-rod fretting wear Kim, Kyu-Tae
2010
6 p. 1386-1391
6 p.
artikel
134 The effect of thermal radiation on the solidification dynamics of metal oxide melt droplets Dombrovsky, Leonid A.
2008
6 p. 1421-1429
9 p.
artikel
135 The effects of heat treatments on the microstructure and mechanical properties of the Ti–2.19Al–2.35Zr alloy Kim, Tae-Hoon
2008
6 p. 1286-1294
9 p.
artikel
136 The hydrodynamic effects of single-phase flow on flow accelerated corrosion in a 90-degree elbow El-Gammal, M.
2010
6 p. 1589-1598
10 p.
artikel
137 The MEGAPIE-TEST project: Supporting research and lessons learned in first-of-a-kind spallation target technology Fazio, C.
2008
6 p. 1471-1495
25 p.
artikel
138 Theoretical study of flashing and water hammer in a supercritical water cycle during pressure drop Imre, A.R.
2010
6 p. 1569-1574
6 p.
artikel
139 Thermal frequency response studies of a hollow cylinder subject to loads of different amplitude and shape Paffumi, E.
2010
6 p. 1355-1362
8 p.
artikel
140 Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model Costa, Antonella L.
2010
6 p. 1487-1494
8 p.
artikel
141 Thermal hydraulic behaviors during loss of shutdown cooling system at HTS opened under LLDS Yuan, J.T.
2011
6 p. 2093-2098
6 p.
artikel
142 Thermal–hydraulic studies related to the design of LBE neutron spallation target for accelerator driven systems Mantha, Vishveshwar
2007
6 p. 607-617
11 p.
artikel
143 Thermoelastic bowing of composite cylindrical fuel rods Hunter, Brook L.
1968
6 p. 487-502
16 p.
artikel
144 The study on a statistical methodology for PWR fuel rod internal pressure evaluation Kim, Kyu-Tae
2010
6 p. 1397-1402
6 p.
artikel
145 The “thousand words” problem: Summarizing multi-dimensional data Scott, David M.
2011
6 p. 1945-1951
7 p.
artikel
146 Towards a better understanding of iodine chemistry in RCS of nuclear reactors Girault, N.
2009
6 p. 1162-1170
9 p.
artikel
147 Towards a-scan imaging via Ultrasonic Vibration Potential measurements Guan, Peng
2011
6 p. 1994-1997
4 p.
artikel
148 Turbulent cooling water discharge into still body of water Ali, Jafar
2011
6 p. 2006-2012
7 p.
artikel
149 Ultrasound Vibration Potential measurement techniques for imaging Schlaberg, H.I.
2011
6 p. 1981-1987
7 p.
artikel
150 Variable friction pendulum system for seismic isolation of liquid storage tanks Panchal, V.R.
2008
6 p. 1304-1315
12 p.
artikel
151 Very-Large Eddy Simulation (V-LES) of the flow across a tube bundle Labois, Mathieu
2011
6 p. 2075-2085
11 p.
artikel
152 Vibration of the fuel assembly of a marine reactor Takada, Y.
1968
6 p. 578-584
7 p.
artikel
153 Vibrations of probe used for the defect detection of helical heating tubes in a fast breeder reactor Inoue, Takumi
2008
6 p. 1459-1470
12 p.
artikel
154 Void measurement using high-resolution gamma-ray computed tomography Bieberle, André
2011
6 p. 2086-2092
7 p.
artikel
155 VVER vessel steel corrosion at interaction with molten corium in oxidizing atmosphere Bechta, S.V.
2009
6 p. 1103-1112
10 p.
artikel
                             155 gevonden resultaten
 
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