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                             23 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A simple novel and fast computational model for the LIVE-L4 Zhang, Y.P.
2013
68 C p. 20-30
11 p.
artikel
2 A zero dimensional model for simulation of TRIGA Mark II dynamic response Cammi, Antonio
2013
68 C p. 43-54
12 p.
artikel
3 Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR) Tian, Y.H.
2013
68 C p. 177-187
11 p.
artikel
4 Comments on the application of bifurcation analysis in BWR stability analysis Lange, Carsten
2013
68 C p. 1-15
15 p.
artikel
5 Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR Chaudri, Khurrum Saleem
2013
68 C p. 55-64
10 p.
artikel
6 Development of a control rod depletion methodology for the Westinghouse NEXUS system Franceschini, Fausto
2013
68 C p. 235-242
8 p.
artikel
7 Development of a thermal hydraulic code for an integral reactor Wang, Z.L.
2013
68 C p. 31-42
12 p.
artikel
8 Editorial Board 2013
68 C p. IFC-
1 p.
artikel
9 Experimental research on the incipient boiling wall superheat of sodium Qiu, Zicheng
2013
68 C p. 121-129
9 p.
artikel
10 Investigation of the MSFR core physics and fuel cycle characteristics Fiorina, Carlo
2013
68 C p. 153-168
16 p.
artikel
11 LOCA analysis of reactor cores with tight lattice using the modified RELAP5 code Wu, Dan
2013
68 C p. 111-120
10 p.
artikel
12 Multi-objective optimal design of vertical natural circulation steam generator Chen, Lei
2013
68 C p. 79-88
10 p.
artikel
13 Nonlinear dynamic output-feedback power-level control for PWRs: A shifted-ectropy based design approach Dong, Zhe
2013
68 C p. 223-234
12 p.
artikel
14 Numerical study on thermal hydraulic performance of a Printed Circuit Heat Exchanger Figley, Justin
2013
68 C p. 89-96
8 p.
artikel
15 Prediction of critical heat flux for water flow in vertical round tubes using support vector regression model Jiang, B.T.
2013
68 C p. 210-222
13 p.
artikel
16 Preliminary study of parameter uncertainty influence on Pressurized Water Reactor core design Wang, Mingjun
2013
68 C p. 200-209
10 p.
artikel
17 Research and design of distributed fault diagnosis system in nuclear power plant Yong-kuo, Liu
2013
68 C p. 97-110
14 p.
artikel
18 Study of XeF2 fluorination potential against SrO, MoO3, and Nb2O5 in TG/DTA for use in reactive gas recycle Inabinett, D.
2013
68 C p. 16-19
4 p.
artikel
19 Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor Wu, Y.W.
2013
68 C p. 65-78
14 p.
artikel
20 Theoretical study on the flow instability of supercritical water in the parallel channels Su, Yali
2013
68 C p. 169-176
8 p.
artikel
21 The thermophysical properties of binary mixtures of molten alkali fluoride salts. Part I: Prediction of thermodynamic properties through use of the Soft-Sphere Equation of State Griffard, Cory
2013
68 C p. 130-141
12 p.
artikel
22 Transient behavior of the sodium–potassium alloy heat pipe in passive residual heat removal system of molten salt reactor Wang, Chenglong
2013
68 C p. 142-152
11 p.
artikel
23 Use of the Soft-Sphere Equation of State to predict the thermodynamic properties of the molten salt mixtures LiF–BeF2, NaF–BeF2, and KF–BeF2 Griffard, Cory
2013
68 C p. 188-199
12 p.
artikel
                             23 gevonden resultaten
 
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