Download or read book An Evaluation of High temperature Gas cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book High Temperature Gas cooled Reactors written by Tetsuaki Takeda and published by Academic Press. This book was released on 2021-02-24 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.

Download or read book An Evaluation of High Temperature Gas cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of Human Error in High Temperature Gas Cooled Reactor written by Waleed Hussain Abul-Faraj and published by . This book was released on 1979 with total page 310 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of Modular High Temperature Gas cooled Reactors written by P. Levin and published by . This book was released on 1994 with total page 61 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Critical Evaluation of High temperature Gas cooled Reactors Applicable to Coal Conversion written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A critical review is presented of the technology and costs of very high-temperature gas-cooled reactors (VHTRs) applicable to nuclear coal conversion. Coal conversion processes suitable for coupling to reactors are described. Vendor concepts of the VHTR are summarized. The materials requirements as a function of process temperature in the range 1400 to 2000°F are analyzed. Components, environmental and safety factors, economics and nuclear fuel cycles are reviewed. It is concluded that process heat supply in the range 1400 to 1500°F could be developed with a high degree of assurance. Process heat at 1600°F would require considerably more materials development. While temperatures up to 2000°F appear to be attainable, considerably more research and risk were involved. A demonstration plant would be required as a step in the commercialization of the VHTR.

Download or read book Evaluation of High Temperature Gas Cooled Reactor Fuel Particle Coating Failure Models and Data written by Michael Tokar and published by . This book was released on 1976 with total page 136 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Evaluation of High Temperature Gas Cooled Reactor Performance written by International Atomic Energy Agency and published by . This book was released on 2013 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents the findings of an IAEA coordinated research project focusing on validation of the safety and operational aspects of high temperature gas cooled reactors under projected and actual operating conditions. This guide documents the results of an analysis of the ASTRA critical facility at the Kurchatov Institute in the Russian Federation.

Download or read book Evaluation of High Temperature Gas cooled Reactor Physics Experiments as VHTR Benchmark Problems written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Utility Industry Evaluation of the Modular High temperature Gas cooled Reactor written by and published by . This book was released on 1990 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Download or read book Accident Delineation and Evaluation of the High temperature Gas cooled Reactor System Concepts written by Beverly W. Washburn and published by . This book was released on 1979 with total page 255 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book An Evaluation of High temperature Gas cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Utility Industry Evaluation of the Modular High temperature Gas cooled Reactor Project 2079 written by Electric Power Research Institute and published by . This book was released on 1990 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Multiphase Flow and Heat Transfer in Pebble Bed Reactor Core written by Shengyao Jiang and published by Springer Nature. This book was released on 2020-11-19 with total page 510 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research advances. The numerical methods and experimental measurements/techniques used to solve pebble flows, as well as the content on radiation modeling for high-temperature pebble beds, will be of particular interest. This book is intended for a broad readership, including researchers and practitioners, and is sure to become a key reference resource for students and professionals alike.

Download or read book Evaluation of Proposed German Safety Criteria for High temperature Gas cooled Reactors written by General Atomic Company and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work reviews proposed safety criteria prepared by the German Bundesministerium des Innern (BMI) for future licensing of gas-cooled high-temperature reactor (HTR) concepts in the Federal Republic of Germany. Comparison is made with US General Design Criteria (GDCs) in 10CFR50 Appendix A and with German light water reactor (LWR) criteria. Implications for the HTR design relative to the US design and safety approach are indicated. Both inherent characteristics and design features of the steam cycle, gas turbine, and process heat concepts are taken into account as well as generic design options such as a pebble bed or prismatic core.

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 IOS Press. This book was released on 2006 with total page 160 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.