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                             26 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Air ingress analysis of chimney effect in the 200MWe pebble-bed modular high temperature gas-cooled reactor Chen, Zhipeng
2017
106 C p. 143-153
11 p.
artikel
2 Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2 Hu, J.
2017
106 C p. 221-234
14 p.
artikel
3 A neutron transport and thermal hydraulics coupling scheme to study xenon induced power oscillations in a nuclear reactor Kitcher, Evans D.
2017
106 C p. 64-70
7 p.
artikel
4 A semi-analytical treatment of xenon oscillations Zarei, M.
2017
106 C p. 127-135
9 p.
artikel
5 A study on different thermodynamic cycle schemes coupled with a high temperature gas-cooled reactor Qu, Xinhe
2017
106 C p. 185-194
10 p.
artikel
6 Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems Pelloni, Sandro
2017
106 C p. 33-50
18 p.
artikel
7 Editorial board 2017
106 C p. IFC-
1 p.
artikel
8 Effects of temperature and pressure on Henry’s law constant for hydrogen in the primary water of a simulated pressurized-water reactor Lee, Eun-Hee
2017
106 C p. 136-142
7 p.
artikel
9 Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method Chang, Seok-Kyu
2017
106 C p. 160-169
10 p.
artikel
10 Experimental study on the thermal stratification in a pool boiling with a horizontal heat source Kim, Seok
2017
106 C p. 235-246
12 p.
artikel
11 Experimental validation of analytic formulas for the statistical uncertainty in the Feynman- α method Dubi, C.
2017
106 C p. 84-90
7 p.
artikel
12 Liquid Salt Test Loop modeling using TRACE Avigni, P.
2017
106 C p. 170-184
15 p.
artikel
13 Mesh-free method for numerical solution of the multi-group discrete ordinate neutron transport equation Kashi, S.
2017
106 C p. 51-63
13 p.
artikel
14 Modified fractional neutron point kinetics equations for finite and infinite medium of bar reactor core Hamada, Yasser Mohamed
2017
106 C p. 118-126
9 p.
artikel
15 Neutron fluence analysis of graphite reflector in SPRR-300 during the whole reactor lifetime Wankui, Yang
2017
106 C p. 91-96
6 p.
artikel
16 Note on the extinction probability Pázsit, Imre
2017
106 C p. 271-272
2 p.
artikel
17 Numerical investigation on heat transfer to supercritical CO2 in rolling motion Zhao, Zhenxing
2017
106 C p. 97-110
14 p.
artikel
18 One-dimensional coolability and concrete ablation analysis of volumetrically heat-generating debris bed Na, Hanbee
2017
106 C p. 256-270
15 p.
artikel
19 Optimal design methods for a digital human-computer interface based on human reliability in a nuclear power plant Jiang, Jianjun
2017
106 C p. 247-255
9 p.
artikel
20 Physical tool for Unprotected Loss Of Flow transient simulations in a Sodium Fast Reactor Droin, Jean-Baptiste
2017
106 C p. 195-210
16 p.
artikel
21 Proposition of innovative and safe design of grid plate for Tehran research reactor Jalali, H.R.
2017
106 C p. 11-32
22 p.
artikel
22 Reactivity effects of the random dispersal of nuclear materials Difilippo, Felix C.
2017
106 C p. 211-220
10 p.
artikel
23 The Generic Containment SB-LOCA accident simulation: Comparison of the parameter uncertainties and user-effect Povilaitis, Mantas
2017
106 C p. 1-10
10 p.
artikel
24 The Monte Carlo GPT methodology for the analysis of ratios of functionals bilinear with the real and adjoint neutron fluxes Burgio, N.
2017
106 C p. 154-159
6 p.
artikel
25 Thermal-hydraulic analyses of the High-Temperature engineering Test Reactor for loss of forced cooling at 30% reactor power Takamatsu, Kuniyoshi
2017
106 C p. 71-83
13 p.
artikel
26 Uncertainty analysis with double heterogeneity treatment based on the generalized perturbation theory Han, Tae Young
2017
106 C p. 111-117
7 p.
artikel
                             26 gevonden resultaten
 
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