Graphite Materials Testing in the ATR for Lifetime Management of Magnox Reactors PDF Download
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
A major feature of the Magnox gas cooled reactor design is the graphite core, which acts as the moderator but also provides the physical structure for fuel, control rods, instrumentation and coolant gas channels. The lifetime of a graphite core is dependent upon two principal aging processes: irradiation damage and radiolytic oxidation. Irradiation damage from fast neutrons creates lattice defects leading to changes in physical and mechanical properties and the accumulation of stresses. Radiolytic oxidation is caused by the reaction of oxidizing species from the carbon dioxide coolant gas with the graphite, these species being produced by gamma radiation. Radiolytic oxidation reduces the density and hence the moderating capability of the graphite, but also reduces strength affecting the integrity of core components. In order to manage continued operation over the planned lifetimes of their power stations, BNFL needed to extend their database of the effects of these two phenomena on their graphite cores through an irradiation experiment. This paper will discuss the background, purpose, and the processes taken and planned (i.e. post irradiation examination) to ensure meaningful data on the graphite core material is obtained from the irradiation experiment.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
A major feature of the Magnox gas cooled reactor design is the graphite core, which acts as the moderator but also provides the physical structure for fuel, control rods, instrumentation and coolant gas channels. The lifetime of a graphite core is dependent upon two principal aging processes: irradiation damage and radiolytic oxidation. Irradiation damage from fast neutrons creates lattice defects leading to changes in physical and mechanical properties and the accumulation of stresses. Radiolytic oxidation is caused by the reaction of oxidizing species from the carbon dioxide coolant gas with the graphite, these species being produced by gamma radiation. Radiolytic oxidation reduces the density and hence the moderating capability of the graphite, but also reduces strength affecting the integrity of core components. In order to manage continued operation over the planned lifetimes of their power stations, BNFL needed to extend their database of the effects of these two phenomena on their graphite cores through an irradiation experiment. This paper will discuss the background, purpose, and the processes taken and planned (i.e. post irradiation examination) to ensure meaningful data on the graphite core material is obtained from the irradiation experiment.
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 88
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Book Description
Graphite has been used as a moderator and reflector of neutrons in more than 100nuclear power plants and in many research and plutonium-production reactors. It is usedprimarily as a neutron reflector or neutron moderator, although graphite is also used for other features of reactor cores, such as fuel sleeves. Many of the graphite-moderated reactors are now quite old, with some already shutdown. Therefore radioactive graphite dismantling and the management of radioactive graphite waste are becoming an increasingly important issue for a number of IAEA Member States. This report provides a comprehensive discussion of radioactive graphite waste characterization, handling, conditioning and disposal throughout the operating and decommissioning life cycle.
Author: Gareth B Neighbour
Publisher: Royal Society of Chemistry
ISBN: 1849735174
Category : Science
Languages : en
Pages : 227
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Book Description
Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during service posing a threat to the functionality of the core, and potentially, the safe operation of the reactor. Thus, the importance of modelling and measuring reactor core graphite properties and performance increases especially as continued use beyond the designed life time becomes significant. This book captures the proceedings from the third in a series of meetings addressing the extensive research and analysis performed to ensure the continuing safe performance of the graphite cores. Covering four broad themes: mechanistic; statistical; empirical; and, plant performance, this book should appeal to a broad range of readers from engineers and reactor operators to policy makers.
Author: Gareth B. Neighbour
Publisher: Royal Society of Chemistry
ISBN: 0854043454
Category : Nature
Languages : en
Pages : 313
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Book Description
This product is not available separately, it is only sold as part of a set. There are 750 products in the set and these are all sold as one entity. This product is not available separately, it is only sold as part of a set. There are 750 products in the set and these are all sold as one entity.
Author: Athanasia Tzelepi
Publisher:
ISBN: 9780803177260
Category : Graphite
Languages : en
Pages : 0
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Book Description
"This compilation of Selected Technical Papers, STP1639, Graphite Testing for Nuclear Applications : The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments, contains peer-reviewed papers that were presented at a symposium held virtually September 23-24, 2021. The symposium was sponsored by ASTM International Committee D02 on Petroleum Products, Liquid Fuels, and Lubricants, and Subcommittee D02.F0 Manufactured Carbon and Graphite Products"--
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc Series No. 1790
ISBN: 9789201040169
Category : Technology & Engineering
Languages : en
Pages : 0
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Book Description
Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.
Author: David Albright
Publisher:
ISBN:
Category : History
Languages : en
Pages : 544
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Book Description
Plutonium and highly enriched uranium (HEU) are the basic materials used in nuclear weapons. Plutonium also plays an important part in the generation of nuclear electricity. Knowing how much plutonium and HEU exists, where and in which form is vital for international security and nuclear commerce. This book is a thorough revision of the World Inventory of Plutonium and highly Enriched Uranium, 1992. It provides a rigorous and comprehensive assessment of the amounts of plutonium and HEU in military and civilian programmes, in nuclear and non-nuclear weapon states, and in countries seeking to acquire nuclear weapons. The capibilities that exist for producing these materials around the world are examined in depth, as are the policy issues raised by them. Containing much new information, this book is indispensable to all those concerned with the great contemporary issues in international nuclear relations: arms reductions in the nuclear weapon states, nuclear proliferation, nuclear smuggling, the roles of plutonium and enriched uranium in the nuclear fuel-cycle, and the disposition of surplus weapon material.
Author: OECD Nuclear Energy Agency
Publisher: OECD
ISBN:
Category : Business & Economics
Languages : en
Pages : 120
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Book Description
As energy demand increases in line with the expansion of the world's leading economies and the growth of developing economies, a key challenge remains of how to provide the energy levels required while protecting our environment and conserving natural resources. Nuclear energy is a complex and controversial technology but also has the potential to provide considerable benefits. This publication explores a range of issues involved in the use of nuclear energy, including safety aspects, whether its use is economically competitive, its role in meeting greenhouse gas reduction targets, how to manage the radioactive waste it generates, whether its use increase the risk of proliferation of nuclear weapons, security of resources, and its potential role in the future.
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.
