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                             59 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A fission collision separation method for efficient incident flux response expansion coefficient generation Zhang, Dingkang
2014
73 C p. 264-269
6 p.
artikel
2 An empirical study on the human error recovery failure probability when using soft controls in NPP advanced MCRs Jang, Inseok
2014
73 C p. 373-381
9 p.
artikel
3 A new method for multi-objective in core fuel management optimization using biogeography based algorithm Khoshahval, Farrokh
2014
73 C p. 294-303
10 p.
artikel
4 A novel fault detection system taking into account uncertainties in the reconstructed signals Al-Dahidi, Sameer
2014
73 C p. 131-144
14 p.
artikel
5 A simple procedure to estimate reactivity with good noise filtering characteristics Shimazu, Yoichiro
2014
73 C p. 392-397
6 p.
artikel
6 A state-of-the-art review of recent advances in supercritical natural circulation loops for nuclear applications Sarkar, Milan K.S.
2014
73 C p. 250-263
14 p.
artikel
7 A variational principle for the Milne problem linear extrapolation length Grzesik, J.A.
2014
73 C p. 382-386
5 p.
artikel
8 Calculation and measurement of neutron flux in internal parts of the VVER-1000 mock-up Košt’ál, Michal
2014
73 C p. 413-422
10 p.
artikel
9 CFD simulating the transient thermal–hydraulic characteristics in a 17×17 bundle for a spent fuel pool under the loss of external cooling system accident Chen, S.R.
2014
73 C p. 241-249
9 p.
artikel
10 Core axial power shape reconstruction based on radial basis function neural network Peng, Xingjie
2014
73 C p. 339-344
6 p.
artikel
11 Coupled 3D neutronics/thermal hydraulics modeling of the SAFARI-1 MTR Rosenkrantz, Adam
2014
73 C p. 122-130
9 p.
artikel
12 Critical heavy water level and some parameters for the HWZPR reactor core using MCNP4c code Nasrabadi, M.N.
2014
73 C p. 496-499
4 p.
artikel
13 Design, in-sodium testing and performance evaluation of annular linear induction pump for a sodium cooled fast reactor Nashine, B.K.
2014
73 C p. 527-536
10 p.
artikel
14 Development and application of a thermal-hydraulics analysis code for small modular natural circulation lead or lead-alloy cooled fast reactors Chen, Zhao
2014
73 C p. 68-74
7 p.
artikel
15 Discontinuous finite element discretizations for the S N neutron transport equation in problems with spatially varying cross sections Maginot, Peter G.
2014
73 C p. 506-526
21 p.
artikel
16 Editorial board 2014
73 C p. IFC-
1 p.
artikel
17 Effect of silica nanoparticles on the stability of decontamination foam and their application for oxide dissolution of corroded specimens Yoon, In-Ho
2014
73 C p. 168-174
7 p.
artikel
18 Effects of cross sections tables generation and optimization on rod ejection transient analyses Sánchez-Cervera, S.
2014
73 C p. 387-391
5 p.
artikel
19 Effects of depth on transport of 129I in crystalline rock Orucoglu, Esra
2014
73 C p. 304-316
13 p.
artikel
20 Ensemble-based sensitivity analysis of a Best Estimate Thermal Hydraulics model: Application to a Passive Containment Cooling System of an AP1000 Nuclear Power Plant Di Maio, Francesco
2014
73 C p. 200-210
11 p.
artikel
21 Experimental investigation of thermal stratification in a pressurizer surge line Qiao, Shouxu
2014
73 C p. 211-217
7 p.
artikel
22 Experimental investigation of void distribution in Suppression Pool during the initial blowdown period of a Loss of Coolant Accident using air–water two-phase mixture Rassame, Somboon
2014
73 C p. 53-67
15 p.
artikel
23 Experimental study of natural convection heat transfer in a volumetrically heated semicircular pool Lee, Jong Kuk
2014
73 C p. 432-440
9 p.
artikel
24 Flow boiling heat transfer in volumetrically heated packed bed Xu, Guangzhan
2014
73 C p. 330-338
9 p.
artikel
25 Flow resistance characteristics of pulsating laminar flow in rectangular channels Zhuang, Nailiang
2014
73 C p. 398-407
10 p.
artikel
26 Fractional neutron point kinetics equations for nuclear reactor dynamics – Numerical solution investigations Nowak, Tomasz Karol
2014
73 C p. 317-329
13 p.
artikel
27 From flatness to steepness: Updating TALYS covariances with experimental information Rochman, D.
2014
73 C p. 7-16
10 p.
artikel
28 Heat transfer research on enhanced heating surfaces in flow boiling in a minichannel and pool boiling Piasecka, Magdalena
2014
73 C p. 282-293
12 p.
artikel
29 High conversion Th-U233 fuel for current generation of PWRs: Part I – Assembly level analysis Baldova, D.
2014
73 C p. 552-559
8 p.
artikel
30 High conversion Th–U233 fuel for current generation of PWRs: Part II – 3D full core analysis Baldova, D.
2014
73 C p. 560-566
7 p.
artikel
31 Hydrodynamics of slug flow in a vertical narrow rectangular channel under laminar flow condition Wang, Yang
2014
73 C p. 465-477
13 p.
artikel
32 Kinetics and equilibrium modeling of uranium(VI) sorption by bituminous shale from aqueous solution Ortaboy, Sinem
2014
73 C p. 345-354
10 p.
artikel
33 Measurements and visualization of velocity profiles in a scaled CANDU6 moderator tank using particle image velocimetry Seo, Han
2014
73 C p. 361-372
12 p.
artikel
34 Modeling the thermal–hydraulic behavior of the reactor cavity cooling system using RELAP5-3D Vaghetto, Rodolfo
2014
73 C p. 75-83
9 p.
artikel
35 Neutronic study of an innovative natural uranium–thorium based fusion–fission hybrid energy system Xiao, S.C.
2014
73 C p. 500-505
6 p.
artikel
36 Note on the comparison of experimental and simulated gamma energy spectra for NaI with 137Cs, 60Co, and 241Am Celiktas, C.
2014
73 C p. 355-360
6 p.
artikel
37 Numerical simulation based on Haar wavelet operational method to solve neutron point kinetics equation involving sinusoidal and pulse reactivity Patra, A.
2014
73 C p. 408-412
5 p.
artikel
38 Numerical simulation of air pollutant dispersion using an in situ tracer experiment at a nuclear site Jeong, Hyojoon
2014
73 C p. 1-6
6 p.
artikel
39 Numerical simulation of the SURC-2 and SURC-4 MCCI experiments by MPS method Li, Xin
2014
73 C p. 46-52
7 p.
artikel
40 Optimization of a moisture separator reheater Li, Guijing
2014
73 C p. 537-546
10 p.
artikel
41 Optimization study of Ultra-long Cycle Fast Reactor core concept Tak, Taewoo
2014
73 C p. 145-161
17 p.
artikel
42 Optimizing variance reduction in Monte Carlo eigenvalue calculations that employ the source iteration approach Burn, Kenneth W.
2014
73 C p. 218-240
23 p.
artikel
43 Prediction of local loss coefficient for turbulent flow in axisymmetric sudden expansions with a chamfer: Effect of Reynolds number Bae, Youngmin
2014
73 C p. 33-38
6 p.
artikel
44 Preliminary study of coupling CFD code FLUENT and system code RELAP5 Li, Wei
2014
73 C p. 96-107
12 p.
artikel
45 Proposal of a new type of two-phase interchannel mixing model for application to subchannel analysis of PWR conditions Pang, Bo
2014
73 C p. 108-121
14 p.
artikel
46 Quasi-differential neutron scattering from 238U from 0.5 to 20MeV Daskalakis, A.M.
2014
73 C p. 455-464
10 p.
artikel
47 Reactor fuel depletion benchmark of TINDER Martin, W.J.
2014
73 C p. 547-551
5 p.
artikel
48 Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities Jeong, KwanSeong
2014
73 C p. 441-445
5 p.
artikel
49 Research on intelligent monitor for 3D power distribution of reactor core Xia, Hong
2014
73 C p. 446-454
9 p.
artikel
50 Seamless remote dismantling system for heavy and highly radioactive components of Korean nuclear power plants Hyun, Dongjun
2014
73 C p. 39-45
7 p.
artikel
51 Stability analysis for single-phase liquid metal rectangular natural circulation loops Lu, Daogang
2014
73 C p. 189-199
11 p.
artikel
52 Structural assessment of intermediate printed circuit heat exchanger for sodium-cooled fast reactor with supercritical CO2 cycle Lee, Youho
2014
73 C p. 84-95
12 p.
artikel
53 The design and fabrication of a small MHD pump for liquid sodium circulation Kim, Hee Reyoung
2014
73 C p. 162-167
6 p.
artikel
54 Theoretical calculations and evaluations of n+ 32,33,34,36,nat.S reactions Wu, Zhendong
2014
73 C p. 17-32
16 p.
artikel
55 Theory and applications of the fission matrix method for continuous-energy Monte Carlo Carney, Sean
2014
73 C p. 423-431
9 p.
artikel
56 Thermal–hydraulic characteristics and flow instability analysis of an HTGR helical tube steam generator Ma, Yue
2014
73 C p. 484-495
12 p.
artikel
57 Unbiased estimators of coincidence and correlation in non-analogous Monte Carlo particle transport Szieberth, M.
2014
73 C p. 270-281
12 p.
artikel
58 Utilizing the burnup capability in MCNPX to perform depletion analysis of an MNSR fuel Boafo, E.K.
2014
73 C p. 478-483
6 p.
artikel
59 Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis Álvarez-Velarde, F.
2014
73 C p. 175-188
14 p.
artikel
                             59 gevonden resultaten
 
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