A Parametric Study of the Gas-cooled Reactor Concept
Author: Hanford Atomic Products Operation
Publisher:
Published: 1958
Total Pages: 44
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DOWNLOAD EBOOK →Author: Hanford Atomic Products Operation
Publisher:
Published: 1958
Total Pages: 44
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DOWNLOAD EBOOK →Author: Hanford Atomic Products Operation. Process Design Operation
Publisher:
Published: 1958
Total Pages: 276
ISBN-13:
DOWNLOAD EBOOK →Author:
Publisher:
Published: 1959
Total Pages:
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DOWNLOAD EBOOK →The results of a parametric study on a gas cooled reactor are repotrtd. The system considered was a heliumcooled, UC/sup 2/-fueled arrargement with fuel assemblies consisting of clusters of long cylindrical elements, each element covered by a stainless steel jacket. The axial power distribution was assumed to be a chopped cosine having an axial peak-to-average power of 1.32. The three parameters of interest in the study were the diameter of coolant channel, pressure drop through core, and pumping Ppwer expended. The analysis is presented for the central channel. (auth).
Author: Chang Oh
Publisher:
Published: 2004
Total Pages:
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DOWNLOAD EBOOK →The Idaho National Engineering and EnvironmentalLaboratory (INEEL) is investigating a Brayton cycle efficiencyimprovement on a high temperature gas-cooled reactor (HTGR)as part of Generation-IV nuclear engineering research initiative. In this project, we are investigating helium Brayton cyclesfor the secondary side of an indirect energy conversion system. Ultimately we will investigate the improvement of the Braytoncycle using other fluids, such as supercritical carbon dioxide. Prior to the cycle improvement study, we established a numberof baseline cases for the helium indirect Brayton cycle. Thesecases look at both single-shaft and multiple-shaftturbomachinary. The baseline cases are based on a 250 MWthermal pebble bed HTGR. The results from this study areapplicable to other reactor concepts such as a very hightemperature gas-cooled reactor (VHTR), fast gas-cooled reactor(FGR), supercritical water reactor (SWR), and others. In this study, we are using the HYSYS computer code foroptimization of the helium Brayton cycle. Besides the HYSYSprocess optimization, we performed parametric study to see theeffect of important parameters on the cycle efficiency. Forthese parametric calculations, we use a cycle efficiency modelthat was developed based on the Visual Basic computerlanguage. As a part of this study we are currently investigatedsingle-shaft vs. multiple shaft arrangement for cycle efficiencyand comparison, which will be published in the next paper. The ultimate goal of this study is to use supercriticalcarbon dioxide for the HTGR power conversion loop in orderto improve the cycle efficiency to values great than that of thehelium Brayton cycle. This paper includes preliminary calculations of the steadystate overall Brayton cycle efficiency based on the pebble bedreactor reference design (helium used as the working fluid) andcompares those results with an initial calculation of a CO2Brayton cycle.
Author: U.S. Atomic Energy Commission
Publisher:
Published: 1960
Total Pages: 386
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DOWNLOAD EBOOK →Author: Willem Frederik Geert van Rooijen
Publisher: Delft University Press
Published: 2006
Total Pages: 164
ISBN-13:
DOWNLOAD EBOOK →The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Author: U.S. Atomic Energy Commission. Division of Reactor Development and Technology
Publisher:
Published: 1972
Total Pages: 56
ISBN-13:
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