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                             31 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analysis of control rod drop accident in PWRs with multipoint kinetics method Parhizkari, H.
2016
88 C p. 194-203
artikel
2 Analytical studies of long-term IRWST injection core cooling under small break LOCA in passive safety PWR Li, Yu Quan
2016
88 C p. 218-236
artikel
3 Analytic derivation of the statistical error in the Feynman- α method Dubi, C.
2016
88 C p. 186-193
artikel
4 A new formulation for the Doppler broadening function relaxing the approximations of Beth–Plackzec Palma, Daniel A.P.
2016
88 C p. 68-72
artikel
5 An investigation of the effect of split-type mixing vane on extent of crossflow between subchannels through the fuel rod gaps Agbodemegbe, V.Y.
2016
88 C p. 174-185
artikel
6 A note on “Comment on the paper: Espinosa-Paredes, et al., 2011. Fractional neutron point kinetics equations for nuclear reactor dynamics. Ann. Nucl. Energy 38, 307–330.” by A.E. Aboanber, A.A. Nahla Espinosa-Paredes, Gilberto
2016
88 C p. 303-304
artikel
7 Assessment of amount and concentration of tritium in HTTR-IS system based on tritium behavior during high-temperature continuous operation of HTTR Dipu, Arnoldus Lambertus
2016
88 C p. 126-134
artikel
8 Attenuation of wall-thinning rate in deep erosion by liquid droplet impingement Fujisawa, Nobuyuki
2016
88 C p. 151-157
artikel
9 Axial dispersion and mixing phenomena of the gas phase in a packed pebble-bed reactor Abdulmohsin, Rahman S.
2016
88 C p. 100-111
artikel
10 Boiling water reactor instability analysis using attractor characteristics Gavilan Moreno, C.J.
2016
88 C p. 41-48
artikel
11 Comment on the paper: Espinosa-Parrdes, et al., 2011. Fractional neutron point kinetics equations for nuclear reactor dynamics. Ann. Nucl. Energ. 38, 307–330 Aboanber, Ahmed E.
2016
88 C p. 301-302
artikel
12 Computing eigenvalue sensitivity coefficients to nuclear data based on the CLUTCH method with RMC code Qiu, Yishu
2016
88 C p. 237-251
artikel
13 Conjugate heat transfer analysis for in-vessel retention with external reactor vessel cooling Park, Jong-Woon
2016
88 C p. 57-67
artikel
14 Control of the nuclear steam generators using adaptive dynamic sliding mode method based on the nonlinear model Ansarifar, G.R.
2016
88 C p. 280-300
artikel
15 Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Hart, Shane W.D.
2016
88 C p. 49-56
artikel
16 Development of a rule-based diagnostic platform on an object-oriented expert system shell Wang, Wenlin
2016
88 C p. 252-264
artikel
17 Editorial board 2016
88 C p. IFC
artikel
18 Evaluation method of iodine re-evolution from an in-containment water pool after a loss of coolant accident, Part II: Evaluation of pH and iodine re-evolution Kim, Tae Hyeon
2016
88 C p. 83-94
artikel
19 General nodal expansion method for multi-dimensional steady and transient convection–diffusion equation Zhou, Xiafeng
2016
88 C p. 118-125
artikel
20 Generation of fission yield covariances to correct discrepancies in the nuclear data libraries Fiorito, L.
2016
88 C p. 12-23
artikel
21 Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method He, Qingming
2016
88 C p. 204-217
artikel
22 Layer-splitting technique for testing the recursive scheme for multilayer shields gamma ray buildup factors Alkhatib, Sari F.
2016
88 C p. 24-29
artikel
23 Modeling of oxide reduction in repeated-batch pyroprocessing Lee, Hyo Jik
2016
88 C p. 1-11
artikel
24 Multi-objective optimization of maintenance programs in nuclear power plants using Genetic Algorithm and Sensitivity Index decision making Ayoobian, Navid
2016
88 C p. 95-99
artikel
25 New burnable absorber for long-cycle low boron operation of PWRs Choe, Jiwon
2016
88 C p. 272-279
artikel
26 Reconsideration of thermal criteria for Korean spent fuel repository Cho, Won-Jin
2016
88 C p. 73-82
artikel
27 RETRACTED: A new strategy to select axial power distribution for thermal hydraulic analysis Kim, Kyung-O
2016
88 C p. 265-271
artikel
28 Safety analyses of 10MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients Gu, Zhixing
2016
88 C p. 112-117
artikel
29 Scram speed assessment for transient analysis in Chinshan BWR-4 Plant Ma, Shao-Shih
2016
88 C p. 30-40
artikel
30 Uncertainty and global sensitivity analysis of neutron survival and extinction probabilities using polynomial chaos Cooling, C.M.
2016
88 C p. 158-173
artikel
31 Validation of the minimalistic Nodal Drift Method for spatial kinetics on a simple CANDU LOCA benchmark Nuttin, A.
2016
88 C p. 135-150
artikel
                             31 gevonden resultaten
 
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