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                             57 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comprehensive evaluation of the RPT method on FCM fuel in light water reactor Zhang, Yunfei

142 C p.
artikel
2 A contamination analysis of the primary coolant system with Monte Carlo simulations Park, Kwangsoo

142 C p.
artikel
3 A critical heat flux model for unilateral heating rectangular narrow channel Song, Gongle

142 C p.
artikel
4 A modified numerical integration method to calculate the view factor between finite and infinite cylinders in arbitrary array Jiang, Chuan

142 C p.
artikel
5 Analysis of post-LOCA long-term core safety characteristics for the Small Modular Reactor ACP100 Deng, Jian

142 C p.
artikel
6 A new method to investigate the boiling two-phase flows by a combination of the three-fluid and drift-flux models Behzadi, M.

142 C p.
artikel
7 A novel reactivity-equivalent physical transformation method for homogenization of double-heterogeneous systems Lou, Lei

142 C p.
artikel
8 A phenomenological CHF model for mixing-vane spacers in a subchannel of a rod bundle Liu, Yang

142 C p.
artikel
9 Application of machine learning methods to predict a thermal conductivity model for compacted bentonite Bang, Hyun-Tae

142 C p.
artikel
10 A quantitative assessment framework for cyber-attack scenarios on nuclear power plants using relative difficulty and consequence Park, Jong Woo

142 C p.
artikel
11 Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor Liu, Xiao

142 C p.
artikel
12 Development of a generative-adversarial-network-based signal reconstruction method for nuclear power plants Kim, Seung Geun

142 C p.
artikel
13 Development of an optimal mitigation strategy by estimating the conditional core damage probability with time-dependent recovery actions Seop Jeon, In

142 C p.
artikel
14 Development of a quantitative method for identifying fault-prone cyber security controls in NPP digital I&C systems Lee, Chanyoung

142 C p.
artikel
15 Development of a Riemann solver for the two-fluid seven-equation model Zhang, Hao

142 C p.
artikel
16 Development of mathematical model for aerosol deposition under jet condition Yan, Xu

142 C p.
artikel
17 3D heterogeneous Cartesian cells for transport-based core simulations Masiello, Emiliano

142 C p.
artikel
18 2D MPS analysis of hydrodynamic fine fragmentation of melt drop with initial steam film during fuel–coolant interaction Li, Gen

142 C p.
artikel
19 Editorial Board
142 C p.
artikel
20 Experimental and theoretical study on fluid-structure interaction and non-equilibrium of the flow through micro cracks Zhang, Jing

142 C p.
artikel
21 Improving variance convergence rate in monte carlo eigenvalue simulations via delayed neutrons Miao, Jilang

142 C p.
artikel
22 Influence of surface wettability increase induced by Gamma-ray irradiation on critical heat flux in downward-facing flow boiling Wang, Laishun

142 C p.
artikel
23 Innovative core design using cobalt-equipped bundles for cobalt-60 production in CANDU6 reactors Lyu, Jinqi

142 C p.
artikel
24 Investigating on multi-RANS models coupling simulation for flow mixing experiments Hu, Peizheng

142 C p.
artikel
25 Investigation of resonance self-shielding effect in PWR cladding material for Zirconium isotopes Xiao, Xiang

142 C p.
artikel
26 Linear energy transfer of fission fragments of 235U and nucleation of gas bubbles in aqueous solutions of uranyl nitrate Winter, George E.

142 C p.
artikel
27 Local impact resistance analysis of prestressed concrete structures considering curvature and post-tensioning effects Chung, Chul-Hun

142 C p.
artikel
28 LQG/LTR controller with simulated annealing algorithm for CIADS core power control Zeng, Wenjie

142 C p.
artikel
29 Monte Carlo simulation of activity concentration measurement of primary coolant of high-temperature gas-cooled pebble-bed modular reactor Lou, Mengqi

142 C p.
artikel
30 Neutron escape probabilities in 3-D reentrant geometries computed using ray tracing Dorville, Joffrey

142 C p.
artikel
31 Neutron heating assessment in Minerve reactor by using alanine/ESR dosimetry Rouihem, F.

142 C p.
artikel
32 Neutronic design study of an integrated space nuclear reactor with Stirling engine Li, Jian

142 C p.
artikel
33 Numerical investigation on performance of moisture separator: Experimental validation, applications and new findings Zhang, Huang

142 C p.
artikel
34 Numerical study on convective heat transfer and friction characteristics of molten salts in circular tubes Zhang, Sheng

142 C p.
artikel
35 Observer based adaptive robust Feedback-linearization control for VVER-1000 nuclear reactors with bounded axial power distribution based on the validated multipoint kinetics reactor model Zaidabadi nejad, M.

142 C p.
artikel
36 Periodic surveillance test strategies to effectively enhance the availability of safety-critical systems in NPPs using the multi-state based availability model Son, Kwang Seop

142 C p.
artikel
37 Physical anomaly detection and identification using Cerenkov radiation Hearne, Jason A.

142 C p.
artikel
38 Physical study of an ultra-long-life small modular fast reactor loaded with U-Pu-Zr fuel Gao, Yucui

142 C p.
artikel
39 Preliminary optimization of emergency core cooling system with accident-tolerant fuels Wu, Di

142 C p.
artikel
40 Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5% Burns, Joseph R.

142 C p.
artikel
41 Reliable leak detection in a heat exchanger of a sodium-cooled fast reactor Guépié, Blaise Kévin

142 C p.
artikel
42 Response function generation for transmutation of Technetium-99 via high energy proton and neutron interactions in MCNP Hearne, Jason A.

142 C p.
artikel
43 Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors Tiberga, Marco

142 C p.
artikel
44 Safety evaluation of the flashing-driven natural circulation IPWR against Loss-of-Feedwater accident Zhao, Yanan

142 C p.
artikel
45 Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests Ferraro, Diego

142 C p.
artikel
46 Space-energy separated representations for multigroup neutron diffusion using proper generalized decompositions Prince, Zachary M.

142 C p.
artikel
47 Sparse Polynomial Chaos expansion for advanced nuclear fuel cycle sensitivity analysis Skarbeli, A.V.

142 C p.
artikel
48 Study of the parameters of the pulse shape method and experimental test of diamond based detector at the VR-1 reactor Novak, Ondrej

142 C p.
artikel
49 Study on the linearization workflow for the generation of point-wise cross sections in nuclear data processing Wan, Chenghui

142 C p.
artikel
50 The application of the moving mesh method in a thermal hydraulic system code Zhao, Xiumei

142 C p.
artikel
51 The correlation analysis of RCPs impeller geometrical parameters and optimization in coast-down process An, Ce

142 C p.
artikel
52 The natural circulation flow characteristic of the core in floating nuclear power plant in rolling motion Li, Ren

142 C p.
artikel
53 Theoretical calculation and evaluation of n + 237,241,243,245Pu reactions Guo, Hairui

142 C p.
artikel
54 Three dimensional reactor power profile reconstruction using Cerenkov radiation Hearne, Jason A.

142 C p.
artikel
55 Two-level time-dependent GET based CMFD acceleration for 3D whole core transient transport simulation using 2D/1D method Kang, Le

142 C p.
artikel
56 Use readings of thermocouples to reconstruct the power distribution of HTR-PM Fan, Kai

142 C p.
artikel
57 Whole plant simulation study on load rejection transient of CPR1000 employing advanced Mechanical Shim strategy Wu, Shifa

142 C p.
artikel
                             57 gevonden resultaten
 
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