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                             22 results found
no title author magazine year volume issue page(s) type
1 A closed-form solution for the two-dimensional transport equation by the LTS N nodal method in the energy range of Compton effect Rodriguez, B.D.A.
2011
38 1 p. 151-156
6 p.
article
2 A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors Pelloni, Sandro
2011
38 1 p. 1-13
13 p.
article
3 A new procedure to generate resonance integral table with an explicit resonance interference for transport lattice codes Kim, Kang-Seog
2011
38 1 p. 118-127
10 p.
article
4 A new radiation shielding material: Amethyst ore Korkut, Turgay
2011
38 1 p. 56-59
4 p.
article
5 Approach for the fission fragment total kinetic energy TKE(A) calculation Manea, V.
2011
38 1 p. 72-79
8 p.
article
6 Azcaxalli: A system based on Ant Colony Optimization algorithms, applied to fuel reloads design in a Boiling Water Reactor Esquivel-Estrada, Jaime
2011
38 1 p. 103-111
9 p.
article
7 Burning plutonium and minimizing radioactive waste in existing PWRs Mittag, S.
2011
38 1 p. 98-102
5 p.
article
8 Calculation and measurement of kinetic parameters of Pakistan Research Reactor-1 (PARR-1) Muhammad, Atta
2011
38 1 p. 44-48
5 p.
article
9 Determination of AKR-2 leakage beam and verification at iron and water arrangements Košťál, Michal
2011
38 1 p. 157-165
9 p.
article
10 Development and application of an extensible engineering simulator for NPP DCS closed-loop test Hou, Dong
2011
38 1 p. 49-55
7 p.
article
11 Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methods van Rooijen, W.F.G.
2011
38 1 p. 133-144
12 p.
article
12 Editorial board 2011
38 1 p. IFC-
1 p.
article
13 GEANT4 simulation of photo-peak efficiency of small high purity germanium detectors for nuclear power plant applications Rehman, Shakeel Ur
2011
38 1 p. 112-117
6 p.
article
14 Graphite reflecting characteristics and shielding factors for Miniature Neutron Source Reactors Albarhoum, M.
2011
38 1 p. 14-20
7 p.
article
15 Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTR Alajo, Ayodeji B.
2011
38 1 p. 88-97
10 p.
article
16 Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations Hong, Ser Gi
2011
38 1 p. 32-43
12 p.
article
17 Methodologies for optimizing ROP detector layout for CANDU® reactors Kastanya, Doddy
2011
38 1 p. 21-31
11 p.
article
18 [No title] Williams, M.M.R.
2011
38 1 p. 166-
1 p.
article
19 NXcom – A program for calculating attenuation coefficients of fast neutrons and gamma-rays El-Khayatt, A.M.
2011
38 1 p. 128-132
5 p.
article
20 parafish: A parallel FE–P N neutron transport solver based on domain decomposition Van Criekingen, S.
2011
38 1 p. 145-150
6 p.
article
21 Spectral zone selection methodology for pebble bed reactors Mphahlele, Ramatsemela
2011
38 1 p. 80-87
8 p.
article
22 Vessel coolant mixing effects on a PWR Main Steam Line Break transient Zerkak, Omar
2011
38 1 p. 60-71
12 p.
article
                             22 results found
 
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