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                             25 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A code development for leak before break (LBB) leakage from supercritical to subcritical conditions Zhang, J.
2018
103 C p. 217-228
artikel
2 Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator Turati, Pietro
2018
103 C p. 176-190
artikel
3 A new study on Uranium (VI) stripping from loaded Alamine 336 using some of alkaline solutions Mir-mohammadi, S.L.
2018
103 C p. 229-235
artikel
4 Assessment of radiation dose received by nuclear plant personnel through a video-based surveillance system Jorge, Carlos Alexandre F.
2018
103 C p. 51-59
artikel
5 Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket Cui, Shijie
2018
103 C p. 8-19
artikel
6 Construction of minor actinides reduction scenario in Japan utilizing fusion reactors Furudate, Yuki
2018
103 C p. 28-32
artikel
7 Design and performance analysis of passive residual heat removal system for a lead-cooled fast reactor Wu, Guowei
2018
103 C p. 236-242
artikel
8 Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC Liu, Zhouyu
2018
103 C p. 114-125
artikel
9 Development of an efficient tightly coupled method for multiphysics reactor transient analysis Senecal, Jaron P.
2018
103 C p. 33-44
artikel
10 Editorial Board 2018
103 C p. ii
artikel
11 Experimental investigation on natural circulation characteristics of emergency passive residual heat removal system in HPR1000 Sun, D.C.
2018
103 C p. 1-7
artikel
12 Flow regime transition criteria for co-current downward two-phase flow Lokanathan, Manojkumar
2018
103 C p. 165-175
artikel
13 Formulation of a fully implicit numerical scheme for simulation of two-phase flow in a vertical channel using the Drift-Flux Model Hajizadeh, A.
2018
103 C p. 91-105
artikel
14 Improvement and optimization of the pseudo-resonant-nuclide subgroup method in NECP-X Liu, Zhouyu
2018
103 C p. 60-73
artikel
15 Laminar fluid flow and heat transfer in non-circular sub-channel geometries of nuclear fuel bundle Moorthi, Annamalai
2018
103 C p. 243-253
artikel
16 Optimization of fuel loading pattern for a material test reactor using swarm intelligence Ahmad, Ammar
2018
103 C p. 45-50
artikel
17 Optimization of regression model using principal component regression method in passive system reliability assessment Solanki, R.B.
2018
103 C p. 126-134
artikel
18 Parametric study of CSR1000 thermal hydraulic stability Shahzad, Muhammad Ali
2018
103 C p. 106-113
artikel
19 Preliminary post-closure safety assessment for a borehole-type repository for disused sealed radioactive sources in Brazil Cota, Stela
2018
103 C p. 74-80
artikel
20 Prospects in China for nuclear development up to 2050 Chen, Yanxin
2018
103 C p. 81-90
artikel
21 Removal of cobalt ions from simulated radioactive wastewater by vacuum membrane distillation Jia, Fei
2018
103 C p. 20-27
artikel
22 Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase Wu, Yingwei
2018
103 C p. 151-164
artikel
23 Simulation of hydrogen generated from fuel bundles and verification of a semi-empirical cladding oxidation model by PWR type CORA tests Ni, Xinghe
2018
103 C p. 191-208
artikel
24 The thermodynamic and cost-benefit-analysis of miniaturized lead-cooled fast reactor with supercritical CO2 power cycle in the commercial market Li, Ming-Jia
2018
103 C p. 135-150
artikel
25 Three-dimensional experiment of heat transfer for molten oxidic pool Chen, Lian
2018
103 C p. 209-216
artikel
                             25 gevonden resultaten
 
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