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                             76 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accelerating a three-dimensional MOC calculation using GPU with CUDA and two-level GCMFD method Zhang, ZhiZhu
2013
62 C p. 445-451
7 p.
artikel
2 Acceleration of low energy nuclear reactions by formation of correlated states of interacting particles in dynamical systems Vysotskii, Vladimir I.
2013
62 C p. 618-625
8 p.
artikel
3 Accelerator Driven Systems (ADSs) for nuclear transmutation Stanculescu, Alexander
2013
62 C p. 607-612
6 p.
artikel
4 Activation cross-sections of longer-lived products of proton induced nuclear reactions on dysprosium up to 36MeV Tárkányi, F.
2013
62 C p. 375-381
7 p.
artikel
5 Activity emission model for VVER 440/213 reactor LOCA Nagy, Attila
2013
62 C p. 413-420
8 p.
artikel
6 A highly accurate algorithm for the solution of the point kinetics equations Ganapol, B.D.
2013
62 C p. 564-571
8 p.
artikel
7 A multi-group neutron noise simulator for fast reactors Tran, Hoai Nam
2013
62 C p. 158-169
12 p.
artikel
8 A multi-scale analysis of the transient behavior of an advanced safety injection tank Yoon, Han Young
2013
62 C p. 17-25
9 p.
artikel
9 Analysis of burn up effects on kinetic parameters in an Accelerator Driven Subcritical TRIGA reactor Hassanzadeh, M.
2013
62 C p. 280-283
4 p.
artikel
10 Analysis of gamma emitting radionuclides (terrestrial and anthropogenic) in soil samples from Kilis province in south Anatolia, Turkey Canbazoğlu, C.
2013
62 C p. 153-157
5 p.
artikel
11 Analysis of magnetic Rayleigh–Taylor instability in a direct energy conversion system which converts inertial fusion plasma kinetic energy into pulsed electrical energy Sijoy, C.D.
2013
62 C p. 81-85
5 p.
artikel
12 Analysis of the MZA/MZB benchmarks with modern nuclear data sets van Rooijen, W.F.G.
2013
62 C p. 504-525
22 p.
artikel
13 Annals of Nuclear Energy – A reminiscence of 40 years by the retiring editor Williams, M.M.R.
2013
62 C p. 536-537
2 p.
artikel
14 A numerical study for the effect of flow skirt geometry on reactor internal flow Lee, Gong Hee
2013
62 C p. 452-462
11 p.
artikel
15 Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface Khvostov, G.
2013
62 C p. 398-412
15 p.
artikel
16 A robust thermal model to investigate radial propagation of core damage due to total instantaneous blockage in SFR fuel subassembly Ravi, L.
2013
62 C p. 342-356
15 p.
artikel
17 Assessment of proliferation resistances of aqueous reprocessing techniques using the TOPS methodology Åberg Lindell, M.
2013
62 C p. 390-397
8 p.
artikel
18 A study of the effectiveness of defense echelon design of ABWR/LMNPP plant for mitigating LOCA accident Huang, Hui-Wen
2013
62 C p. 333-341
9 p.
artikel
19 A thorium loaded external neutron source driven setup as a multipurpose tool for nuclear power Pacan, A.
2013
62 C p. 109-116
8 p.
artikel
20 Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores Fridman, E.
2013
62 C p. 129-136
8 p.
artikel
21 Benchmarking an expert fault detection and diagnostic system on the Three Mile Island accident event sequence Cilliers, A.C.
2013
62 C p. 326-332
7 p.
artikel
22 Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor Fiorina, C.
2013
62 C p. 26-39
14 p.
artikel
23 Comparison of neutron diffusion and Monte Carlo simulations of a fission wave Osborne, A.G.
2013
62 C p. 269-273
5 p.
artikel
24 Correction factor for the experimental prompt neutron decay constant Talamo, Alberto
2013
62 C p. 421-428
8 p.
artikel
25 Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal–hydraulic feedback Dufek, Jan
2013
62 C p. 260-263
4 p.
artikel
26 Development of neutronics and thermal hydraulics coupled code – SAC-RIT for plate type fuel and its application to reactivity initiated transient analysis Singh, Tej
2013
62 C p. 61-80
20 p.
artikel
27 Development of time-dependent reaction rates to optimise predictor–corrector algorithm in ALEPH burn-up code Fiorito, L.
2013
62 C p. 307-315
9 p.
artikel
28 Editorial board 2013
62 C p. IFC-
1 p.
artikel
29 Effective use of local and global component of neutron noise signals Rama Rao, A.
2013
62 C p. 123-128
6 p.
artikel
30 Effects of applying the doppler broadened rejection correction method for LEU and MOX pin cell depletion calculations Trumbull, Timothy H.
2013
62 C p. 184-194
11 p.
artikel
31 Enrichment of 6Li using dispersive liquid–liquid microextraction as a highly efficient technique Davoudi, Mehrdad
2013
62 C p. 499-503
5 p.
artikel
32 Evaluating the effects of cooling schedule on the performance of ADORE Kastanya, Doddy
2013
62 C p. 483-486
4 p.
artikel
33 Evaluation of integral quantities in an accelerator driven system using different nuclear models implemented in the MCNPX Monte Carlo transport code Şarer, Başar
2013
62 C p. 382-389
8 p.
artikel
34 FDBACE code for fast Doppler broadening ACE format based on parallel processing Zangian, M.
2013
62 C p. 170-177
8 p.
artikel
35 Geant4 code for simulation attenuation of gamma rays through scintillation detectors Medhat, M.E.
2013
62 C p. 316-320
5 p.
artikel
36 Heterogeneous reactor core transport technique using response matrix and collision probability methods Safarzadeh, O.
2013
62 C p. 137-143
7 p.
artikel
37 Implementation of a direct perturbation method in MCNP and application to SCALE verification Trottier, A.
2013
62 C p. 291-297
7 p.
artikel
38 Improvement of ATHLET modelling capability for asymmetric natural circulation phenomenon using uncertainty and sensitivity measures Liu, X.J.
2013
62 C p. 471-482
12 p.
artikel
39 Inhibition of iron corrosion in high temperature stagnant liquid lead: A molecular dynamics study Arkundato, Artoto
2013
62 C p. 298-306
9 p.
artikel
40 In situ borehole heater test at the KAERI Underground Research Tunnel in granite Kwon, Sangki
2013
62 C p. 526-535
10 p.
artikel
41 Investigation of nuclear power plant behaviour at low power and cold conditions during an overpressurization in primary circuit Groudev, Pavlin
2013
62 C p. 231-241
11 p.
artikel
42 Measurement of thermal neutron cross section and resonance integral for 148Nd(n,γ)149Nd reaction by using a 55Mn monitor Karadag, Mustafa
2013
62 C p. 274-279
6 p.
artikel
43 Modeling of a highly enriched 235U fission chamber for spent fuel assay Borella, A.
2013
62 C p. 224-230
7 p.
artikel
44 More efficient integrated safeguards by applying a reasonable detection probability for maintaining low presence probability of undetected nuclear proliferating activities Otsuka, Naoto
2013
62 C p. 572-576
5 p.
artikel
45 Neutronic and thermohydraulic characteristics of a new breeding thorium–uranium mixed SCWR fuel assembly Liu, Shichang
2013
62 C p. 429-436
8 p.
artikel
46 Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback Brown, Nicholas R.
2013
62 C p. 548-557
10 p.
artikel
47 Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients Brown, Nicholas R.
2013
62 C p. 538-547
10 p.
artikel
48 Neutron sources and transmutation of nuclear waste Ripani, M.
2013
62 C p. 590-595
6 p.
artikel
49 Nodal dynamics modeling of AP1000 reactor for control system design and simulation Wang, P.F.
2013
62 C p. 208-223
16 p.
artikel
50 Non probabilistic solution of uncertain neutron diffusion equation for imprecisely defined homogeneous bare reactor Chakraverty, S.
2013
62 C p. 251-259
9 p.
artikel
51 Nuclear data for radioactive waste management Sartori, Enrico
2013
62 C p. 579-589
11 p.
artikel
52 Nuclear fusion in ordered crystal targets bombarded by monochromatic beams of light or middle-mass isotopes Vysotskii, Vladimir I.
2013
62 C p. 613-617
5 p.
artikel
53 On eigenvalue problems of the one-speed neutron transport equation for isotropic scattering Suragan, D.
2013
62 C p. 468-470
3 p.
artikel
54 On-line reactivity calculation using Lagrange method Malmir, Hessam
2013
62 C p. 463-467
5 p.
artikel
55 Photon attenuation coefficients and shielding effects of Jordanian building materials Sharaf, J.M.
2013
62 C p. 50-56
7 p.
artikel
56 Phytoremediation options for radioactively contaminated sites evaluated Vandenhove, Hildegarde
2013
62 C p. 596-606
11 p.
artikel
57 Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers Jung, Yeon Sang
2013
62 C p. 357-374
18 p.
artikel
58 Reactivity insertion transient analysis for KUR low-enriched uranium silicide fuel core Shen, Xiuzhong
2013
62 C p. 195-207
13 p.
artikel
59 Self-adaptive global best harmony search algorithm applied to reactor core fuel management optimization Poursalehi, N.
2013
62 C p. 86-102
17 p.
artikel
60 Spatial recondensation using the Discrete Generalized Multigroup method Everson, Matthew S.
2013
62 C p. 487-498
12 p.
artikel
61 Study of nuclear gas fuel for a nuclear engine with cylinder and piston structure, using Monte Carlo method Haghani Dogahe, A.
2013
62 C p. 117-122
6 p.
artikel
62 Study of the boron homogenizing process employing an experimental low-pressure bench simulating the IRIS reactor pressurizer – Part II Bezerra, Jair de Lima
2013
62 C p. 558-563
6 p.
artikel
63 Sub-channel analysis of 8×8 and 9×9 BWR fuel assemblies with different two-phase flow models Hashemi-Tilehnoee, M.
2013
62 C p. 264-268
5 p.
artikel
64 Synergistic extraction of gadolinium from nitrate media by mixtures of bis (2,4,4-trimethylpentyl) dithiophosphinic acid and di-(2-ethylhexyl) phosphoric acid Torkaman, R.
2013
62 C p. 284-290
7 p.
artikel
65 The light controlled fusion Gong, BingXin
2013
62 C p. 57-60
4 p.
artikel
66 The results of the irradiation experiment MARIOS on americium transmutation D’Agata, E.
2013
62 C p. 40-49
10 p.
artikel
67 Thermal neutron albedo measurements for multilithic reflectors Mehboob, Khurram
2013
62 C p. 1-7
7 p.
artikel
68 Thermal neutron cross section and resonance integral measurements for the 133Cs(n,γ)134mCs reaction Karadag, Mustafa
2013
62 C p. 178-183
6 p.
artikel
69 The Stresa database: A token for the future Pla, Patricia
2013
62 C p. 8-16
9 p.
artikel
70 The theoretical approach for viscous and end effects on an MHD pump for sodium circulation Kim, Hee Reyoung
2013
62 C p. 103-108
6 p.
artikel
71 Time discretization of the point kinetic equations using matrix exponential method and First-Order Hold Park, Yujin
2013
62 C p. 437-444
8 p.
artikel
72 Transient thermal hydraulic analysis of the IAEA 10MW MTR reactor during Loss of Flow Accident to investigate the flow inversion AL-Yahia, Omar S.
2013
62 C p. 144-152
9 p.
artikel
73 Transmutation of stable isotopes and deactivation of radioactive waste in growing biological systems Vysotskii, Vladimir I.
2013
62 C p. 626-633
8 p.
artikel
74 Uncertainty evaluation of reliability of safety grade decay heat removal system of Indian prototype fast breeder reactor Kumawat, H.L.
2013
62 C p. 242-250
9 p.
artikel
75 Undersampling diagnostics by fission matrix in Monte Carlo criticality calculations She, Ding
2013
62 C p. 321-325
5 p.
artikel
76 X-rays shine light on environmental clean-up: Using synchrotron-based techniques for bioremediation 2013
62 C p. 577-578
2 p.
artikel
                             76 gevonden resultaten
 
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