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                             25 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A class-based search for the in-core fuel management optimization of a pressurized water reactor Meneses, Anderson Alvarenga de Moura
2010
37 11 p. 1554-1560
7 p.
artikel
2 A coupled analysis of system thermal-hydraulics and three-dimensional reactor kinetics for a 12-finger control element assembly drop event in a PWR plant Jeong, Jae Jun
2010
37 11 p. 1580-1587
8 p.
artikel
3 A design study on Pb-208 cooled compact CANDLE burning reactor for future nuclear energy supply Okawa, Tsuyoshi
2010
37 11 p. 1620-1625
6 p.
artikel
4 Analytical reconstruction scheme for the coarse-mesh solution generated by the spectral nodal method for neutral particle discrete ordinates transport model in slab geometry Barros, Ricardo C.
2010
37 11 p. 1461-1466
6 p.
artikel
5 A new technique for Milne’s problem with specular and diffuse reflecting boundary Degheidy, A.R.
2010
37 11 p. 1443-1446
4 p.
artikel
6 A response-based time-dependent neutron transport method Pounders, Justin M.
2010
37 11 p. 1595-1600
6 p.
artikel
7 Benchmarking of evaluated nuclear data for uranium by a 14.8MeV neutron leakage spectra experiment with slab sample Nie, Yangbo
2010
37 11 p. 1456-1460
5 p.
artikel
8 Calculation and analysis of n+90,91,92,94,96,natZr reactions in the E n ⩽250MeV energy range Su, Xinwu
2010
37 11 p. 1513-1526
14 p.
artikel
9 Computational fluid dynamic investigations and experimental validation of frozen seal sodium valve assembly of a fast reactor Velusamy, K.
2010
37 11 p. 1423-1434
12 p.
artikel
10 Design of the thermal neutron beam for neutron radiography at the Syrian MNSR Shaaban, Ismail
2010
37 11 p. 1588-1594
7 p.
artikel
11 Editorial board 2010
37 11 p. IFC-
1 p.
artikel
12 Experimental determination of subcriticality at subcritical PWRs in Korea Lee, E.K.
2010
37 11 p. 1601-1608
8 p.
artikel
13 Experimental investigation on critical heat flux in horizontal channel for low pressure low flow (LPLF) condition Prabhul, K.
2010
37 11 p. 1467-1475
9 p.
artikel
14 Identification of initiating events for pressurized water reactor accidents Hsiao, Te-Yung
2010
37 11 p. 1502-1512
11 p.
artikel
15 Interpretation of the VENUS VIP-BWR program with APOLLO2.8 reference and optimized MOC schemes for 8×8 UO2 and MOX BWR assemblies Blaise, P.
2010
37 11 p. 1609-1619
11 p.
artikel
16 In vessel neutron instrumentation for sodium-cooled fast reactors: Type, lifetime and location Filliatre, P.
2010
37 11 p. 1435-1442
8 p.
artikel
17 Neutronic study of nanofluids application to VVER-1000 Hadad, K.
2010
37 11 p. 1447-1455
9 p.
artikel
18 [No title] Williams, M.M.R.
2010
37 11 p. 1626-1627
2 p.
artikel
19 Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study García-Herranz, N.
2010
37 11 p. 1570-1579
10 p.
artikel
20 Nuclear mechanism for TRU burning oxide fueled core in Advanced Recycling Reactor Ikeda, Kazumi
2010
37 11 p. 1476-1485
10 p.
artikel
21 On the potential use of F2Be-molten-salt for hybrid reactors Lafuente, A.
2010
37 11 p. 1561-1569
9 p.
artikel
22 Pulse height distributions from deterministic radiation transport simulations Benz, Jacob
2010
37 11 p. 1486-1493
8 p.
artikel
23 Reliability assessment method for NPP digital I&C systems considering the effect of automatic periodic tests Lee, Seung Jun
2010
37 11 p. 1527-1533
7 p.
artikel
24 TRACE code modeling of the horizontal steam generator of the PACTEL facility and calculation of a loss-of-feedwater experiment Vihavainen, J.
2010
37 11 p. 1494-1501
8 p.
artikel
25 Validation of the sodium void reactivity effect prediction using JEFF-3.1 nuclear data Tommasi, J.
2010
37 11 p. 1534-1553
20 p.
artikel
                             25 gevonden resultaten
 
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