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                             89 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 AFEN method and its solutions of the hexagonal three-dimensional VVER-1000 benchmark problem Lee, Jaejun
2006
8 p. 880-890
11 p.
artikel
2 A hybrid method for the simulation of radionuclide contaminant plumes in heterogeneous unsaturated formations Aquino, J.
2011
8 p. 1159-1166
8 p.
artikel
3 Alternative forms of the time-dependent neutron transport equation Coppa, G.G.M.
2008
8 p. 934-938
5 p.
artikel
4 A model for predicting static instability in two-phase flow systems Farhadi, Kazem
2009
8 p. 805-812
8 p.
artikel
5 Analyses of the V1000CT-1 benchmark with the DYN3D/ATHLET and DYN3D/RELAP coupled code systems including a coolant mixing model validated against CFD calculations Kliem, S.
2006
8 p. 830-848
19 p.
artikel
6 Analysis of gypsum ore conversion with aid of gamma-ray transmission and CCRD Vasconcelos, Wagner Eustaquio de
2011
8 p. 1185-1189
5 p.
artikel
7 Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code Bousbia Salah, Anis
2006
8 p. 806-819
14 p.
artikel
8 Analytical approach to the neutron kinetics of the non-homogeneous reactor Corno, S.E.
2008
8 p. 847-865
19 p.
artikel
9 An analytical solution of the point kinetics equations with time-variable reactivity by the decomposition method Petersen, Claudio Z.
2011
8 p. 1091-1094
4 p.
artikel
10 An assessment of RELAP5/Mod3.3 condensation model for high Reynolds number flows Ağlar, Fahri
2010
8 p. 759-766
8 p.
artikel
11 Another option for separated plutonium management: Storage MOX Macfarlane, Allison M.
2007
8 p. 644-650
7 p.
artikel
12 An overview of the Boltzmann transport equation solution for neutrons, photons and electrons in Cartesian geometry Rodriguez, Bárbara D.d.A.
2011
8 p. 1119-1125
7 p.
artikel
13 A Particle Swarm Optimization (PSO) approach for non-periodic preventive maintenance scheduling programming Pereira, Cláudio M.N.A.
2010
8 p. 710-714
5 p.
artikel
14 Application of the MTSVD unfolding method for reconstruction of primary X-ray spectra using semiconductor detectors Gallardo, S.
2011
8 p. 1136-1139
4 p.
artikel
15 A Preface from Red Impact Wallenius, J.
2007
8 p. 567-
1 p.
artikel
16 ASTEC V1.3 code SOPHAEROS module validation using the STORM experiments Bujan, A.
2010
8 p. 777-788
12 p.
artikel
17 A tribute to Bruno Montagnini, Professor of Nuclear Reactor Physics, University of Pisa Ravetto, Piero
2008
8 p. 845-846
2 p.
artikel
18 Ceramic matrices for plutonium disposition Ewing, Rodney C.
2007
8 p. 635-643
9 p.
artikel
19 Comparative RELAP5-3D analysis in support of the NPP DBA analysis in Ukraine Shkarupa, A.
2006
8 p. 891-911
21 p.
artikel
20 Comparison of RELAP5 calculations of VVER-1000 coolant transient benchmark phase 1 at different power Stefanova, Antoaneta E.
2006
8 p. 790-805
16 p.
artikel
21 Computational design and preliminary measurements of a mixed-field irradiation facility Giusti, V.
2008
8 p. 877-885
9 p.
artikel
22 Cost–benefit analysis of BeO–UO2 nuclear fuel Kim, S.K.
2010
8 p. 813-821
9 p.
artikel
23 Deduction of a symmetric tensor formulation of the PN method for the linear transport equation Coppa, G.
2010
8 p. 747-752
6 p.
artikel
24 Delayed-gamma signature calculation for neutron-induced fission and activation using MCNPX, Part III: Transport theory Durkee Jr., Joe W.
2009
8 p. 837-844
8 p.
artikel
25 Delayed-gamma signature calculation for neutron-induced fission and activation using MCNPX. Part II: Simulations Durkee Jr., Joe W.
2009
8 p. 828-836
9 p.
artikel
26 Delayed-gamma signature calculation for neutron-induced fission and activation using MCNPX, Part I: Theory Durkee Jr., Joe W.
2009
8 p. 813-827
15 p.
artikel
27 Determination of a test section parameters for IRIS nuclear reactor pressurizer Bezerra da Silva, Mário Augusto
2011
8 p. 1181-1184
4 p.
artikel
28 Determination of the effective delayed neutron fraction for training reactor VR-1 Michálek, Svetozár
2010
8 p. 735-742
8 p.
artikel
29 Development of integrated dose assessment program for accident analysis of LILW managed in temporary storage facility Ahn, Min Ho
2010
8 p. 837-849
13 p.
artikel
30 Editorial Board 2009
8 p. IFC-
1 p.
artikel
31 Editorial Board 2010
8 p. IFC-
1 p.
artikel
32 Editorial Board 2007
8 p. IFC-
1 p.
artikel
33 Editorial Board 2008
8 p. IFC-
1 p.
artikel
34 Editorial Board 2011
8 p. IFC-
1 p.
artikel
35 Evaluation of a numeric procedure for flow simulation of a 5 × 5 PWR rod bundle with a mixing vane spacer Navarro, Moysés A.
2011
8 p. 1190-1196
7 p.
artikel
36 Evaluation of the effects of gamma radiation on physical and chemical characterisitics of pineapple (Ananas comosus (L.) Meer) cv. Smooth Cayenne minimally processed Perecin, T.N.
2011
8 p. 1145-1147
3 p.
artikel
37 Examination of uranium and plutonium solution criticality in high-concentration solutions Kornreich, Drew E.
2010
8 p. 830-836
7 p.
artikel
38 Existence theory for a one-dimensional problem arising from the boundary layer analysis of radiative flows de Azevedo, F.S.
2011
8 p. 1105-1113
9 p.
artikel
39 Experimental and operational validation of burn-up calculations for the Syrian MNSR Omar, H.
2010
8 p. 753-758
6 p.
artikel
40 French experiences and perspectives on plutonium recycling in the existing power fleet Bernard, Patrice
2007
8 p. 583-588
6 p.
artikel
41 Fuel cycle strategies and plutonium management in Europe Haas, D.
2007
8 p. 574-582
9 p.
artikel
42 Full-core SSCWR calculations applying a fast computational method Reiss, T.
2010
8 p. 767-776
10 p.
artikel
43 HEXTRAN–SMABRE calculation of the VVER-1000 coolant transient-1 benchmark Syrjälahti, Elina
2006
8 p. 849-864
16 p.
artikel
44 Impact of cross-section generation procedures on the simulation of the VVER-1000 pump startup experiment in the OECD/DOE/CEA V1000CT benchmark by coupled 3D thermal-hydraulics/neutron kinetics models Ivanov, Boyan D.
2006
8 p. 746-763
18 p.
artikel
45 Implementation of control rod movement and boron injection options by using control variables in RELAP5/PARCS V2.7 coupled code Miró, R.
2011
8 p. 1084-1090
7 p.
artikel
46 Influence of gamma radiation on properties of common Brazilian wood species used in artwork Severiano, Lucio C.
2010
8 p. 730-734
5 p.
artikel
47 Introduction to the special issue on the OECD/DOE/CEA V1000CT-1 benchmark Ivanov, Kostadin N.
2006
8 p. 727-
1 p.
artikel
48 Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS Espinoza, Sánchez
2006
8 p. 865-879
15 p.
artikel
49 Lesson learned from the adoption of numerical techniques in the analysis of nuclear reactor thermal-hydraulic phenomena Ambrosini, Walter
2008
8 p. 866-876
11 p.
artikel
50 Measurements of the isothermal, power and temperature reactivity coefficients of the IPR-R1 TRIGA reactor Souza, Rose Mary Gomes do Prado
2011
8 p. 1126-1131
6 p.
artikel
51 Model-based calculations of the probability of a country’s nuclear proliferation decisions Li, Jun
2010
8 p. 789-808
20 p.
artikel
52 Modelling effects and their impact on the results of ATHLET solutions of Exercise 1 of the VVER-1000 Coolant Transient Benchmark Langenbuch, S.
2006
8 p. 912-921
10 p.
artikel
53 Multigroup caseology in 1D via the Fourier transform Ganapol, B.D.
2008
8 p. 886-907
22 p.
artikel
54 Neutron production in the operation of a 16.5MeV PETrace cyclotron Gallerani, R.
2008
8 p. 939-943
5 p.
artikel
55 New accounting system for liability provisions and Radioactive Waste Management Act in Korea Kim, S.K.
2010
8 p. 822-829
8 p.
artikel
56 Nonlinear analysis of nuclear coupled density wave instability in time domain for a boiling water reactor core undergoing core-wide and regional modes of oscillations Dutta, Goutam
2009
8 p. 769-787
19 p.
artikel
57 NRI Řež solution of Exercise 3 of VVER-1000 Coolant Transient Benchmark – Phase 1 with coupled codes DYN3D–ATHLET Hádek, Jan
2006
8 p. 820-829
10 p.
artikel
58 OECD/DOE/CEA VVER-1000 coolant transient (V1000CT) benchmark – A consistent approach for assessing coupled codes for RIA analysis Ivanov, Boyan D.
2006
8 p. 728-745
18 p.
artikel
59 Performance of a transmutation advanced device for sustainable energy application García, C.
2011
8 p. 1151-1158
8 p.
artikel
60 Plutonium management and Generation IV systems Lennox, T.A.
2007
8 p. 589-596
8 p.
artikel
61 Plutonium management with thorium-based fuels and inert matrix fuels in thermal reactor systems Schram, R.P.C.
2007
8 p. 617-622
6 p.
artikel
62 Plutonium solubility and self-irradiation effects in borosilicate glass Deschanels, X.
2007
8 p. 623-634
12 p.
artikel
63 Polyclonal antibody to ovomucoid determination in gamma irradiated laying eggs Harder, M.N.C.
2011
8 p. 1148-1150
3 p.
artikel
64 Preface Barros, Ricardo C.
2011
8 p. 1083-
1 p.
artikel
65 Present status of nuclear containments and ISI in Korea Park, Jihong
2009
8 p. 761-768
8 p.
artikel
66 Principal component analysis in an experimental cold flow model of a fluid catalytic cracking unit by gammametry dos Santos, V.A.
2011
8 p. 1114-1118
5 p.
artikel
67 Production of polymer-plaster composite by gamma irradiation Gazineu, Maria Helena Paranhos
2011
8 p. 1140-1144
5 p.
artikel
68 Reactivity balance in the IPR-R1 TRIGA reactor Souza, Rose Mary Gomes do Prado
2011
8 p. 1132-1135
4 p.
artikel
69 REA 3D-dynamic analysis in Almaraz NPP with RELAP5/PARCS v2.7 and SIMTAB cross-sections tables Barrachina, T.
2011
8 p. 1167-1180
14 p.
artikel
70 Reducing radiotoxicity in the long run Westlén, Daniel
2007
8 p. 597-605
9 p.
artikel
71 Semi 2D modeling of the horizontal steam generator PGV-1000 using the RELAP5 code Zarifi, E.
2009
8 p. 788-798
11 p.
artikel
72 Simulation of the VVER-1000 pump start-up experiment in the OECD/DOE/CEA V1000CT benchmark by the FLICA4/CRONOS2 coupled code system Aniel-Buchheit, Sylvie
2006
8 p. 773-789
17 p.
artikel
73 Simulation of the VVER-1000 pump start-up experiment of the OECD V1000CT benchmark with CATHARE and TRAC-PF1 Kolev, N.
2006
8 p. 922-936
15 p.
artikel
74 Solution of the nonlinear point nuclear reactor kinetics equations Nahla, Abdallah A.
2010
8 p. 743-746
4 p.
artikel
75 Some reflections on the age of experts in the nuclear energy sector von Estorff, Ulrik
2010
8 p. 707-709
3 p.
artikel
76 Subchannel analysis of CANDU-SCWR fuel Li, Changying
2009
8 p. 799-804
6 p.
artikel
77 The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part II: Model assessment and application Tran, Chi-Thanh
2009
8 p. 860-871
12 p.
artikel
78 The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part I: Physical processes, modeling and model implementation Tran, Chi-Thanh
2009
8 p. 849-859
11 p.
artikel
79 The management of separated plutonium: An introduction Nuttall, William J.
2007
8 p. 568-573
6 p.
artikel
80 The quasi-static method revisited Dulla, Sandra
2008
8 p. 908-920
13 p.
artikel
81 Thermal power calibrations of the IPR-R1 TRIGA reactor by the calorimetric and the heat balance methods Mesquita, Amir Zacarias
2011
8 p. 1197-1203
7 p.
artikel
82 Thermodynamic and transport properties in non-equilibrium argon, oxygen and nitrogen thermal plasmas Colombo, V.
2008
8 p. 921-933
13 p.
artikel
83 Thermohydraulic features of the use of U3Si LEU fuel in low-power research reactors Albarhoum, M.
2010
8 p. 809-812
4 p.
artikel
84 Thoria and inert matrix fuels for a sustainable nuclear power Lombardi, C.
2008
8 p. 944-953
10 p.
artikel
85 Transfer function modelling of the Lead-cooled Fast Reactor (LFR) dynamics Colombo, Marco
2010
8 p. 715-729
15 p.
artikel
86 Transmutation capabilities of the CERN Energy Amplifier System Kadi, Yacine
2007
8 p. 606-616
11 p.
artikel
87 Use of poly(methyl methacrylate) in radioactive waste management: II. Monte Carlo simulations Özdemir, Tonguç
2009
8 p. 845-848
4 p.
artikel
88 Valuation of BWR stability operating in natural circulation conditions Soares, Humberto V.
2011
8 p. 1095-1104
10 p.
artikel
89 VVER-1000 radial reflector modeling by diffusion nodes Petkov, Petko T.
2006
8 p. 764-772
9 p.
artikel
                             89 gevonden resultaten
 
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