Subchannel Analysis of Wire Wrapped SCWR Assembly [PDF]
Science and Technology of Nuclear Installations, 2014 Application of wire wrap spacers in SCWR can reduce pressure drop and obtain better mixing capability. As a consequence, the required coolant pumping power is decreased and the coolant temperature profile inside the fuel bundle is flattened which will ...
Jianqiang Shan +5 more
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Joint subchannel power allocation for downlink NOMA systems based on quantum carnivorous plant algorithm [PDF]
Journal of King Saud University - Computer and Information SciencesCurrently, most existing research on non-orthogonal multiple access (NOMA) systems converts power allocation into two independent procedures, i.e., inter-subchannel power allocation and intra-subchannel power allocation.
Hongyuan Gao
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Application of CUPID for subchannel-scale thermal–hydraulic analysis of pressurized water reactor core under single-phase conditions [PDF]
Nuclear Engineering and Technology, 2018 There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a light water reactor under accident conditions. Considering the computing
Seok Jong Yoon +4 more
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SUBSALS: a subchannel thermal-hydraulic code for IRT type fuel analysis [PDF]
Acta Polytechnica CTU Proceedings, 2022 The LVR-15 research reactor is operated with a tube type fuel IRT-4M. Due to fuel’s unique concentric square annular shape with, coolant flow is subject to significant pressure driven crossflow.
Tomáš Adámek
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MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA [PDF]
Acta Polytechnica CTU Proceedings, 2018 This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids.
Vojtěch Caha, Jiří Čížek
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Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies [PDF]
He jishuBackgroundSubchannel analysis of fuel assemblies is critical for the development of lead-bismuth reactors.PurposeThis study aims to modify and optimize the COBRA subchannel program to make it suitable for lead-bismuth reactors and validate its ...
WANG Yan +4 more
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Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA [PDF]
Science and Technology of Nuclear Installations, 2012 In the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5
Dae-Hyun Hwang +3 more
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Fuel, Core Design and Subchannel Analysis of a Superfast Reactor [PDF]
Journal of Nuclear Science and Technology, 2008 A compact supercritical water-cooled fast reactor (superfast reactor) core with a power of 700MWe is designed by using a three-dimensional neutronics thermal-hydraulic coupled method. The core consists of 126 seed assemblies and 73 blanket assemblies.
Liangzhi Cao +2 more
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ANALYSIS OF FUEL LONGTERM EFFECTS USING SUBCHANNEL CODES
Journal of Engineering, 2010 Thermohydraulic computer codes such as COBRA3C are now becoming in practical use as part of power plant licensing process. One of the areas of interest to reactor designer is the effect due to longterm operations and the changes that might occur either ...
E.A. AMIN , M.Y. ABDUL-AHAD
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Analysis of Subchannel and Rod Bundle PSBT Experiments with CATHARE 3 [PDF]
Science and Technology of Nuclear Installations, 2012 This paper presents the assessment of CATHARE 3 against PWR subchannel and rod bundle tests of the PSBT benchmark. Noticeable measurements were the following: void fraction in single subchannel and rod bundle, multiple liquid temperatures at subchannel ...
M. Valette
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