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                             22 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A data-driven approach for predicting failure scenarios in nuclear systems Zio, Enrico
2010
37 4 p. 482-491
10 p.
artikel
2 Analysis of 99mTc-RBC labeling efficiency between modified in-vitro method and AMC method Ryu, Jae-Kwang
2010
37 4 p. 529-533
5 p.
artikel
3 A source efficient ADS for minor actinides burning Fokau, Andrei
2010
37 4 p. 540-545
6 p.
artikel
4 Calculation, measurement and sensitivity analysis of kinetic parameters of Tehran Research Reactor Hosseini, S.A.
2010
37 4 p. 463-470
8 p.
artikel
5 Data-driven controller of nuclear steam generators by set membership approximation Ahmad, Zuheir
2010
37 4 p. 512-521
10 p.
artikel
6 Degradation mechanism of check valves in nuclear power plants Lee, Sun-Ki
2010
37 4 p. 621-627
7 p.
artikel
7 Dynamic impact characteristics of KN-18 SNF transport cask – Part 1: An advanced numerical simulation and validation technique Kim, Kap-Sun
2010
37 4 p. 546-559
14 p.
artikel
8 Dynamic impact characteristics of KN-18 SNF transport cask – Part 2: Sensitivity analysis of modeling and design parameters Kim, Kap-Sun
2010
37 4 p. 560-571
12 p.
artikel
9 Dynamic model of Fast Breeder Test Reactor Vaidyanathan, G.
2010
37 4 p. 450-462
13 p.
artikel
10 Editorial board 2010
37 4 p. IFC-
1 p.
artikel
11 Eigenvalue sensitivity to system dimensions Favorite, Jeffrey A.
2010
37 4 p. 522-528
7 p.
artikel
12 Evaluation of the proximity effect on flow-accelerated corrosion Ahmed, Wael H.
2010
37 4 p. 598-605
8 p.
artikel
13 Experimental analysis for neutron multiplication by using reaction rate distribution in accelerator-driven system Shahbunder, Hesham
2010
37 4 p. 592-597
6 p.
artikel
14 Hydrodynamic transition delay in rectangular channels under high heat flux Silin, N.
2010
37 4 p. 615-620
6 p.
artikel
15 Implementation of a second-order upwind method in a semi-implicit two-phase flow code on unstructured meshes Cho, H.K.
2010
37 4 p. 606-614
9 p.
artikel
16 Mixed-dual implementations of the simplified P n method Hébert, Alain
2010
37 4 p. 498-511
14 p.
artikel
17 Numerical prediction of the fission product plate-out for a VHTR application Yoo, Jun Soo
2010
37 4 p. 471-481
11 p.
artikel
18 “Point by Point” model calculation of prompt neutron emission data for 248Cm(SF) and 244Cm(SF) Tudora, Anabella
2010
37 4 p. 492-497
6 p.
artikel
19 Simulation of uncontrolled loss of flow transients of a material test research reactor fuelled with low and high enriched uranium dispersion fuels Muhammad, Farhan
2010
37 4 p. 582-591
10 p.
artikel
20 The OKTAVIAN TOF experiments in SINBAD: Evaluation of the experimental uncertainties Milocco, Alberto
2010
37 4 p. 443-449
7 p.
artikel
21 Theoretical cross sections of 209Bi, 232Th, 235U and 238U on deuteron-induced reactions Büyükuslu, H.
2010
37 4 p. 534-539
6 p.
artikel
22 Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code Omar, H.
2010
37 4 p. 572-581
10 p.
artikel
                             22 gevonden resultaten
 
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