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                             34 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A Hybrid Transport Point-Kinetic method for simulating source transients in subcritical systems Picca, Paolo
2011
38 12 p. 2680-2688
9 p.
artikel
2 An acceleration technique for 2D MOC based on Krylov subspace and domain decomposition methods Zhang, Hongbo
2011
38 12 p. 2742-2751
10 p.
artikel
3 Analysis of hydrogen risk mitigation with passive autocatalytic recombiner system in CPR1000 NPP during a hypothetical station blackout Huang, X.G.
2011
38 12 p. 2762-2769
8 p.
artikel
4 Analysis of laminar to turbulent transition of pulsating flow in ocean environment with energy gradient method Yan, B.H.
2011
38 12 p. 2779-2786
8 p.
artikel
5 Analysis of shape isomer yields of heavy elements in the framework of dynamical-statistical model Eslamizadeh, H.
2011
38 12 p. 2806-2809
4 p.
artikel
6 An efficient technique for the point reactor kinetics equations with Newtonian temperature feedback effects Nahla, Abdallah A.
2011
38 12 p. 2810-2817
8 p.
artikel
7 An experimental study of the shielding characteristics of the dwelling house building materials against gamma radiations in the Central Region of Syria Albarhoum, M.
2011
38 12 p. 2824-2829
6 p.
artikel
8 An Interval Bound Algorithm of optimizing reactor core loading pattern by using reactivity interval schema Gong, Zhaohu
2011
38 12 p. 2787-2796
10 p.
artikel
9 A three-dimensional thermal and fluid dynamics analysis of a gas cooled subcritical fast reactor driven by a D–T fusion neutron source Angelo, G.
2011
38 12 p. 2734-2741
8 p.
artikel
10 Bubble viscosity effect on internal circulation within the bubble rising due to buoyancy using the level set method Ansari, M.R.
2011
38 12 p. 2770-2778
9 p.
artikel
11 Burnup management simulator for small and medium sized reactors Krishna Kumar, P.T.
2011
38 12 p. 2840-2842
3 p.
artikel
12 Calculation of the power distribution in the fuel rods of the low power research reactor using the MCNP4C code Dawahra, S.
2011
38 12 p. 2859-2862
4 p.
artikel
13 Comment on the paper “Post-Shutdown decay power and radionuclide inventories in the discharged fuels of HEU and potential LEU miniature neutron source reactors” by Mirza et al. [Ann. Nucl. Energy 37 (2010) 701–706] Chamgordani, H.Kh.
2011
38 12 p. 2863-2864
2 p.
artikel
14 CORE SIM: A multi-purpose neutronic tool for research and education Demazière, Christophe
2011
38 12 p. 2698-2718
21 p.
artikel
15 Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportions Gencel, Osman
2011
38 12 p. 2719-2723
5 p.
artikel
16 Determination of Tehran Research Reactor power by 16N gamma detection Armozd, Hamid Reza
2011
38 12 p. 2667-2672
6 p.
artikel
17 Editorial board 2011
38 12 p. IFC-
1 p.
artikel
18 Hot point detection method Gandini, A.
2011
38 12 p. 2843-2847
5 p.
artikel
19 Identification of an equivalent electrical model to a natural circulation BWR core model Valle-Hernández, Julio
2011
38 12 p. 2848-2858
11 p.
artikel
20 Impact of cross section libraries on CASMO-4E and CASMO-4 results Rantamäki, K.M.
2011
38 12 p. 2830-2835
6 p.
artikel
21 Loss of flow accident and its mitigation measures for nuclear systems with SCWR-M Xu, Zhihong
2011
38 12 p. 2634-2644
11 p.
artikel
22 MgO single-crystal as an efficient thermal neutron filter Adib, M.
2011
38 12 p. 2673-2679
7 p.
artikel
23 Model development and simulation of transient behavior of helium turbine system Xie, Heng
2011
38 12 p. 2797-2805
9 p.
artikel
24 Photoneutron production and backscattering in high density concretes used for radiation therapy shielding Mesbahi, Asghar
2011
38 12 p. 2752-2756
5 p.
artikel
25 Plutonium isotopic composition of high burnup spent fuel discharged from light water reactors Nakano, Yoshihiro
2011
38 12 p. 2689-2697
9 p.
artikel
26 Reactivity feedback coefficients of a low enriched uranium fuelled material test research reactor at end-of-life Muhammad, Farhan
2011
38 12 p. 2836-2839
4 p.
artikel
27 Reformation of hazardous wastes into useful supporting materials for fast reactor fuels Osaka, Masahiko
2011
38 12 p. 2661-2666
6 p.
artikel
28 Response to: Comment on the paper “Post-Shutdown decay power and radionuclide inventories in the discharged fuels of HEU and potential LEU miniature neutron source reactors” by Mirza, S.M., Khan, A., Mirza N.M. [Ann. Nucl. Energy 37 (2010) 701–706] Mirza, Nasir M.
2011
38 12 p. 2865-2866
2 p.
artikel
29 Sampling based uncertainty analysis of station blackout in PSB VVER integral test facility Dubey, S.K.
2011
38 12 p. 2724-2733
10 p.
artikel
30 Steady-state neutronic analysis of converting the UK CONSORT reactor for ADS experiments Owen, Hywel
2011
38 12 p. 2653-2660
8 p.
artikel
31 The Davidson method as an alternative to power iterations for criticality calculations Subramanian, C.
2011
38 12 p. 2818-2823
6 p.
artikel
32 Thermal hydraulic performance analysis of a double tube bundle steam generator for a liquid metal reactor Kim, Eui-Kwang
2011
38 12 p. 2625-2633
9 p.
artikel
33 Thermo-hydraulic reasons for the Local Power Range Monitor (LPRM) spiking Gavilán Moreno, Carlos J.
2011
38 12 p. 2645-2652
8 p.
artikel
34 Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some libraries Günay, Mehtap
2011
38 12 p. 2757-2761
5 p.
artikel
                             34 gevonden resultaten
 
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