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                             20 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method Yun, Sunghwan
2010
37 12 p. 1649-1658
10 p.
artikel
2 Accuracy of criticality calculations made using current nuclear data libraries for MOX fuelled fast critical assemblies Rowlands, J.L.
2010
37 12 p. 1666-1673
8 p.
artikel
3 Comparative cost analysis of direct disposal versus pyro-processing with DUPIC in Korea Lee, Jewhan
2010
37 12 p. 1699-1704
6 p.
artikel
4 Core and sub-channel analysis of SCWR with mixed spectrum core Liu, X.J.
2010
37 12 p. 1674-1682
9 p.
artikel
5 Core design improvement by optimizing the control and protection system elements distribution Hosein Fadaei, Amir
2010
37 12 p. 1640-1648
9 p.
artikel
6 Cross-section parameterization of the pebble bed modular reactor using the dimension-wise expansion model Živanović, Rastko
2010
37 12 p. 1763-1773
11 p.
artikel
7 Design, construction and simulation of a multipurpose system for precision movement of control rods in nuclear reactors Shirazi, S.A. Mousavi
2010
37 12 p. 1659-1665
7 p.
artikel
8 Editorial board 2010
37 12 p. IFC-
1 p.
artikel
9 Effects of neutron spectrum and external neutron source on neutron multiplication parameters in accelerator-driven system Shahbunder, Hesham
2010
37 12 p. 1785-1791
7 p.
artikel
10 Experimental validation of radial reconstructed pin-power distributions in full-scale BWR fuel assemblies with and without control blade Giust, Flavio
2010
37 12 p. 1629-1639
11 p.
artikel
11 Fuel management optimization based on power profile by Cellular Automata Fadaei, Amir Hosein
2010
37 12 p. 1712-1722
11 p.
artikel
12 Investigation of the symmetry properties and level density parameters of some superdeformed light even–even nuclei Sönmezoğlu, Savaş
2010
37 12 p. 1735-1741
7 p.
artikel
13 Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition Yang, Xingbo
2010
37 12 p. 1723-1734
12 p.
artikel
14 Optimization of in-core fuel management strategy of Tehran Research Reactor (TRR) using MCNP-4C Keyvani, M.
2010
37 12 p. 1683-1687
5 p.
artikel
15 Radiation dose estimation and mass attenuation coefficients of marble used in Turkey Cevik, U.
2010
37 12 p. 1705-1711
7 p.
artikel
16 Risk assessment on hazards for decommissioning safety of a nuclear facility Jeong, Kwan-Seong
2010
37 12 p. 1751-1762
12 p.
artikel
17 Simulation of transient flow caused by pump failure: Point-Implicit Method of Characteristics Rohani, M.
2010
37 12 p. 1742-1750
9 p.
artikel
18 Some remarks on the fissile isotopes Ronen, Yigal
2010
37 12 p. 1783-1784
2 p.
artikel
19 Thermal-fluid assessment of the design options for reactor vessel cooling in a prismatic core VHTR Kim, Min-Hwan
2010
37 12 p. 1774-1782
9 p.
artikel
20 Validation of lattice code ‘EXCEL’ with TIC experiments on uniform and regularly perturbed lattices Ramakrishna, A.
2010
37 12 p. 1688-1698
11 p.
artikel
                             20 gevonden resultaten
 
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