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 |