Download or read book A Parametric Study of the Gas cooled Reactor Concept written by Hanford Atomic Products Operation and published by . This book was released on 1958 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book An Addendum to a Parametric Study of the Gas cooled Reactor Concept written by Hanford Atomic Products Operation. Process Design Operation and published by . This book was released on 1958 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A PARAMETRIC STUDY OF A GAS COOLED REACTOR written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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).

Download or read book Parametric Investigation of Brayton Cycle for High Temperature Gas Cooled Reactor written by Chang Oh and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Download or read book Civilian Power Reactor Program Addendum Core parameter studies for selected reactor types written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 386 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Gas cooled Reactors written by and published by . This book was released on 1959 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by Delft University Press. This book was released on 2006 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Download or read book TID written by and published by . This book was released on 1958 with total page 378 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Parametric Study of the Dynamic Behaviour and Stability of a Steam cooled Fast Reactor with an Integrated Coolant Cycle written by F. Erbacher and published by . This book was released on 1967 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Parametric Study of Monte Carlo based Fuel Burnup for a Sodium Cooled Fast Reactor Core written by Kevin J. Kramer and published by . This book was released on 2007 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Power Reactor Technology written by and published by . This book was released on 1957 with total page 888 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Technical Aspects of the Report on the Gas cooled Graphite moderated Reactor written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1958 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book An Evaluation of the Gas Cooled Fast Reactor written by U.S. Atomic Energy Commission. Division of Reactor Development and Technology and published by . This book was released on 1972 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Energy Research Abstracts written by and published by . This book was released on 1986 with total page 616 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book PARAMETRIC STUDY OP THE DYNAMIC BEHAVIOUR AND STABILITY OF A STEAM COOLED FAST REACTOR WITH AN INTEGRATED COOLING CYCLE written by and published by . This book was released on 1967 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: