Results 151 to 160 of about 4,217 (206)

Modified Dynamic Decode-and-Forward Relaying Protocol for Type II Relay in LTE-Advanced and Beyond. [PDF]

PLoS One, 2016
Nam SS, Alouini MS, Choi S.
europepmc   +1 more source

Resource allocation Of 5G mmWave communication under random interference. [PDF]

Sci Rep
Yuan L, Chen H, Huang Q, Gong J.
europepmc   +1 more source

Activation of Einstein-Podolsky-Rosen steering sharing with unsharp nonlocal measurements. [PDF]

Sci Rep
Han XH, Qian T, Dong SC, Wang S, Xiao Y, Gu YJ.   +5 more
europepmc   +1 more source

Macrophage/microglia-dependent mechanisms drive retinal pigment epithelium regeneration in zebrafish. [PDF]

Cell Rep
Leach LL, Gonzalez RG, Jayawardena SU, Gross JM.   +3 more
europepmc   +1 more source

Reinforcement Learning-Based Resource Allocation Scheme of NR-V2X Sidelink for Joint Communication and Sensing. [PDF]

Sensors (Basel)
Li Z, Wang P, Shen Y, Li S.
europepmc   +1 more source

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Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code

Journal of Nuclear Science and Technology, 1995
Void fraction measurement tests for BWR fuel assemblies have been conducted as part of a Japanese national project. The aim was to verify the current BWR void fraction prediction method. Void fraction was measured using an X-ray CT scanner. This paper describes typical results of void fraction distribution measurements and compares subchannel-averaged ...
Akira INOUE, Tatsuo KUROSU, Toshimasa AOKI, Makoto YAGI, Toru MITSUTAKE, Shin-ichi MOROOKA   +5 more
exaly   +2 more sources

Development of a thermal-hydraulic subchannel analysis code for motion conditions

Progress in Nuclear Energy, 2016
Abstract Since the conventional subchannel analysis codes are designed for the land-based reactor core, a thermal-hydraulic subchannel analysis code was developed to evaluate thermal-hydraulic characteristics of the reactor core under motion conditions. The verification of the code was performed with experimental data and commercial codes.
Rong Cai, Nina Yue, Ronghua Chen, W.X. Tian, G.H. Su, S.Z. Qiu   +5 more
exaly   +2 more sources

Code-to-Code Verification of Thermal Hydraulic Subchannel Code LINDEN

Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance
Abstract The subchannel code LINDEN is developed as a dedicated numerical tool for thermal-hydraulic analyses of a pressurized water reactor (PWR) under varying operating conditions. To fully achieve the development goals of LINDEN, rigorous verification and validation (V&V) work should be included in preparation for its intended ...
Zixuan Wang, Yuanbing Zhu, Yan Wang
exaly   +2 more sources

Development of multiphase subchannel code with new numerical method in COSINE code package

Annals of Nuclear Energy, 2023
Qichao Ma
exaly   +2 more sources