Methods of Analyses for the Chemical Characterization of High Temperature Gas-cooled Reactor Fuel PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Various methods are described which are used to characterize HTGR coated fuel particles and fuel rods. The advantages and accuracy limitations of the various techniques are discussed. (DG).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Various methods are described which are used to characterize HTGR coated fuel particles and fuel rods. The advantages and accuracy limitations of the various techniques are discussed. (DG).
Author: Tetsuaki Takeda Publisher: Academic Press ISBN: 012821032X Category : Business & Economics Languages : en Pages : 478
Book Description
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.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201253101 Category : Business & Economics Languages : en Pages : 639
Book Description
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.
Author: United States. Energy Research and Development Administration. Technical Information Center Publisher: ISBN: Category : Force and energy Languages : en Pages : 724
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
OXIDE-3 is an evolving code developed to analyze the transient response of certain state variables of a High Temperature Gas Cooled Reactor (HTGR) during an accident involving the inleakage of steam and/or air into the helium primary coolant system. Primary tasks of the code are to calculate the primary coolant constituents as a function of time, their resultant chemical interaction with the graphite fuel elements, and their possible egress into the containment building. The report takes a critical look at certain aspects of the problem solving methods implemented in OXIDE-3 and gives estimates of the expected accuracy. Attendant to the latter finding, some of the calculated output may require careful interpretation since programmatical warnings are not given when an accuracy limitation is exceeded. The code has been used at BNL in an investigation to calculate the full power steady state impurity concentrations in the primary coolant system as a function of steam leak rate, steam graphite reaction rate, and the effective diffusion constant of steam in graphite. The results are in reasonable agreement with those obtained from the steady state oxidation code GOPTWO.
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Author: C. E. Hedrick
Author: Tetsuaki Takeda
Author: International Atomic Energy Agency
Author: United States. Energy Research and Development Administration. Technical Information Center
Author: United States. Energy Research and Development Administration
Author: United States. Energy Research and Development Administration
Author: ![Analysis of the Methods Utilized in OXIDE-3. [HTGR]. PDF](https://books.google.com/books/content/images/frontcover/zwNjAQAACAAJ?fife=w80-h100)
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