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                             30 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Accident scenario analysis and control scheme design for a micro Molten Salt Reactor Cui, D.Y.

172 C p.
artikel
2 Accident simulation and control strategy of feedwater system of sodium-cooled fast reactor Sun, Aodi

172 C p.
artikel
3 AI-driven non-intrusive uncertainty quantification of advanced nuclear fuels for digital twin-enabling technology Kobayashi, Kazuma

172 C p.
artikel
4 An adaptive navigation model for path finding in radioactive environment Li, Mengkun

172 C p.
artikel
5 Analysis of the correlation for energy deposition in PWR coolant by coupled neutron-photon transport calculations Castagna, Christian

172 C p.
artikel
6 An integrated assessment method of real-time source term for high temperature gas-cooled reactor Liu, Ao

172 C p.
artikel
7 A simulation study of the ability to detect power distribution perturbations in the texas A&M TRIGA reactor with self-powered neutron detectors Birri, Anthony

172 C p.
artikel
8 Changes in chemical composition of TixAl1−xN coatings immersed in oxygen-saturated Lead–Bismuth Eutectic at low and moderate temperatures (250 °C ≤ T ≤ 410 °C) Serag, Essam

172 C p.
artikel
9 Corrosion behaviors of Inconel 617 and Incoloy 800H in impure helium with different CO contents at high temperatures Zheng, Wei

172 C p.
artikel
10 Developed concrete reinforced by waste of lead fishing weights and steel nails as gamma rays and neutrons shields for nuclear power reactors Oan, Ahmed Faisal

172 C p.
artikel
11 Development and adaptation of meta-heuristic optimization methods in nuclear fuel management of soluble boron-free system-integrated modular advanced reactor to effectively increase the operation cycle length Jafari, Amir Karimi

172 C p.
artikel
12 Development of Modelica-based one-dimensional thermodynamic cycle library and its application in simulation and multi-objective optimization of a He–Xe closed-Brayton-cycle system Zhang, Ao

172 C p.
artikel
13 Dynamic mode decomposition coupled with multilevel octree grid algorithm for large-scale discrete ordinates neutron transport calculations Wang, Jiaxing

172 C p.
artikel
14 Editorial Board
172 C p.
artikel
15 Experimental study of IVR-ERVC CHF limits for CAP1400 Yan, Jinquan

172 C p.
artikel
16 Experiment study on the flow mechanism of the molten pool relocation using simulant materials at room temperature Zhao, Xinhai

172 C p.
artikel
17 Modeling gamma detectors in OpenMC: Validation of a newly implemented pulse-height tally Fichtlscherer, Christopher

172 C p.
artikel
18 Numerical approximation of a two-dimensional fractional neutron diffusion model describing dynamics of neutron flux in a nuclear reactor Roul, P.

172 C p.
artikel
19 Numerical simulation study of boiling Critical Heat Flux characteristics of graphene nanofluids Hou, Yandong

172 C p.
artikel
20 Performance analysis of indirect contact heat pipe radiator for space nuclear power system Li, Zengen

172 C p.
artikel
21 Quantitative analysis of contributing factors to the resilience of emergency response organizations in nuclear power plants Kim, Jaehyun

172 C p.
artikel
22 Sensitivity and uncertainty analyses for advanced nuclear systems (ALFRED, ASTRID, ESFR and MYRRHA) Panizo, S.

172 C p.
artikel
23 Simultaneous use of bismuth trioxide and mill scale for ternary blended geopolymer composite in radiation shielding applications Sharma, Rahul

172 C p.
artikel
24 Supercharging performance of anti-cavitation schemes in pool-type reactor: Experimental verification and numerical investigation Ma, Fubing

172 C p.
artikel
25 Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition Wei, Pengbo

172 C p.
artikel
26 The potential of bi2– xZrxO3+x/2@ZrO2 (BZO) as a heavyweight radiation shielding material: Fabrication and characterization using a hydrothermal technique directly from zircon mineral Mahmoud, K.A.

172 C p.
artikel
27 Thermal and hydraulic characteristics analysis of horizontal lead-bismuth reactor assembly based on sub-channel analysis code Zhang, Yixin

172 C p.
artikel
28 Thermodynamic performance of an innovative space nuclear Brayton cycle with S–N2O Miao, Xinyu

172 C p.
artikel
29 Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions Berry, L.

172 C p.
artikel
30 Ultrasound-assisted removal of contaminants on stainless steel surfaces using nitrogen ultrafine bubble water Nakahara, Masaumi

172 C p.
artikel
                             30 gevonden resultaten
 
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