Digitale Bibliotheek
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                             17 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Adjoint Monte Carlo neutron transport using cross-section probability table representation Diop, Cheikh M’Backé
2010
37 9 p. 1186-1196
11 p.
artikel
2 A probabilistic study of the effect of retardation factor uncertainty using a compartment model for radionuclide release into the biosphere Hagues, A.W.
2010
37 9 p. 1197-1207
11 p.
artikel
3 A sensitivity study on fast reactor scenarios with various conversion ratios Jeong, Chang Joon
2010
37 9 p. 1229-1235
7 p.
artikel
4 CANDU refuelling optimization by successive two-step mathematical programming – I: MILP models for refuelling channel selection Zhang, Shaohong
2010
37 9 p. 1146-1159
14 p.
artikel
5 Computational fluid dynamic analysis of core bypass flow phenomena in a prismatic VHTR Sato, Hiroyuki
2010
37 9 p. 1172-1185
14 p.
artikel
6 Editorial board 2010
37 9 p. IFC-
1 p.
artikel
7 Fluorination of UF4 in a mini-tapered fluidized bed and mathematical modeling Khani, M.H.
2010
37 9 p. 1241-1247
7 p.
artikel
8 Investigating the effect of task complexities on the response time of human operators to perform the emergency tasks of nuclear power plants Park, Jinkyun
2010
37 9 p. 1160-1171
12 p.
artikel
9 [No title] Weaver, D.R.
2010
37 9 p. 1261-1262
2 p.
artikel
10 SHTV, as a technique for core calculation using spatial homogenization and temperature variation Moghaddam, Nader Maleki
2010
37 9 p. 1129-1138
10 p.
artikel
11 Subcritical multiplication factor and source efficiency in accelerator-driven system Shahbunder, Hesham
2010
37 9 p. 1214-1222
9 p.
artikel
12 Sub-critical reactor kinetics analysis using incomplete gamma functions and binomial expansions Sathiyasheela, T.
2010
37 9 p. 1248-1253
6 p.
artikel
13 The use of WIMS and CITATION codes in fuel loading required for the conversion of HEU MNSR core to LEU Azande, T.S.
2010
37 9 p. 1223-1228
6 p.
artikel
14 Transport model based on three-dimensional cross-section generation for TRIGA core analysis Kriangchaiporn, N.
2010
37 9 p. 1254-1260
7 p.
artikel
15 Use of the local Pu-239 concentration as an indicator of burnup spectral history in DYN3D Bilodid, I.
2010
37 9 p. 1208-1213
6 p.
artikel
16 Validation of the Monte Carlo model supporting core conversion of the Portuguese Research Reactor (RPI) for neutron fluence rate determinations Fernandes, A.C.
2010
37 9 p. 1139-1145
7 p.
artikel
17 Vapor explosions: Prediction of a critical liquid–corium velocity in vapor destabilization mechanism of corium melt in the fuel–coolant interactions – FCI Arias, F.J.
2010
37 9 p. 1236-1240
5 p.
artikel
                             17 gevonden resultaten
 
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