Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 96

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Book Description

Author: R. H. Armstrong
Publisher:
ISBN:
Category : Chemical reactions
Languages : en
Pages : 60

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Book Description
A study was made of approximately 132 reports on gas-cooled reactors and related subjects. Charts and tables containing the following information are included: all available reactor information, reactor flow diagrams of suggested concepts, possible core arrangement at core cross section, typical fuel and moderator cell, possible fuel types for unit fuel cell, the properties of materials for moderators and reflectors. the compatibility of gases and base fuel materials at maximum surface temperatures, maximum interface temperatures of fuel elements and core-jacket combinations, allowable operating temperatures and compatibility of gases and various metals. preferences for gas coolants, cost and availability of gases plant thermal cycle efficiencies, thermal properties of gases, pumping power and reactor coolant inlet temperatures, obtainable heat fluxes, composition and physical properties of potential cladding materials. atomic and thermal properties of cladding materials, fabrication characteristics and costs of cladding materials, possible process applications of gases at high temperature, and potential high-temperature materials. The various categories of gas-cooled reactors and examples of each type are discussed. A gas reactor program for high-temperature experimentation is proposed.

Author: Kurt Kugeler
Publisher: Springer
ISBN: 3662577127
Category : Technology & Engineering
Languages : en
Pages : 903

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Book Description
"Modular High-temperature Gas-cooled Reactor Power Plant" introduces the power plants driven by modular high temperature gas-cooled reactors (HTR), which are characterized by their inherent safety features and high output temperatures. HTRs have the potential to be adopted near demand side to supply both electricity and process heat, directly replacing conventional fossil fuels. The world is confronted with two dilemmas in the energy sector, namely climate change and energy supply security. HTRs have the potential to significantly alleviate these concerns. This book will provide readers with a thorough understanding of HTRs, their history, principles, and fields of application. The book is intended for researchers and engineers involved with nuclear engineering and energy technology.

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
Several concepts are being evaluated in the US HTR Program to explore designs which might improve the commercial viability of nuclear power. The general approach is to reduce the reactor power and increase the ability to use inherent features for removing heat following extreme accidents. The unit size and design of these concepts are constrained so that extreme accidents do not result in significant release of radioactivity from the reactor plant. Through the greater reliance on inherent safety features in small HTRs, it should be possible to minimize the amount of nuclear grade components required in the balance-of-plant, which could lead to an economic system. Four HTR concepts are presently being evaluated within the US Program, and these concepts are briefly summarized. A modular HTR using a steel pressure vessel, which is very similar to one of the four HTR concepts being evaluated within the US National program, is presented as an example of a specific concept to illustrate the features and performance of HTRs having a high degree of inherent safety.

Author:
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 218

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Book Description

Author: United States. Congress. Joint Committee on Atomic Energy
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 102

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Book Description

Author: Willem Frederik Geert van Rooijen
Publisher: IOS Press
ISBN: 9781586036966
Category : Technology & Engineering
Languages : en
Pages : 160

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Book Description
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: K. Inoue
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 94

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Book Description

Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 236

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Book Description

Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639

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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.