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                             8 results found
no title author magazine year volume issue page(s) type
1 Calculation of the cross-sections for fast neutrons and gamma-rays in concrete shields El-Sayed Abdo, A.
 2002
 29 16 p. 1977-1988
12 p.
 article
2 Design of an overmoderated fuel and a full MOX core for plutonium consumption in boiling water reactors François, Juan Luis
 2002
 29 16 p. 1953-1965
13 p.
 article
3 Determination of the safety importance of systems of the Tehran research reactor using a PSA method Ghofrani, M.B
 2002
 29 16 p. 1989-2000
12 p.
 article
4 Double-strata high burnup fuel performance in light water reactors Barchevtsev, Vladimir
 2002
 29 16 p. 1919-1932
14 p.
 article
5 Neutronic analysis of PROMETHEUS reactor fueled with various compounds of thorium and uranium Yapıcı, Hüseyin
 2002
 29 16 p. 1871-1889
19 p.
 article
6 On the use of the conjugate gradient method for the solution of the neutron transport equation Gupta, Anurag
 2002
 29 16 p. 1933-1951
19 p.
 article
7 Parallel channel instabilities in boiling water reactor systems: boundary conditions for out of phase oscillations Muñoz-Cobo, J.L.
 2002
 29 16 p. 1891-1917
27 p.
 article
8 Sensitivity analysis for AHWR fuel cluster parameters using different WIMS libraries Kumar, Arvind
 2002
 29 16 p. 1967-1975
9 p.
 article
                             8 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands