Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201109200
Category : Technology & Engineering
Languages : en
Pages : 56

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Book Description
The limitation of 235U enrichment is a current concern among IAEA Member States. In response, work has been undertaken to provide a platform to facilitate a comprehensive review of the current status, prospects and challenges associated with the use of fuels having enrichments higher than 5 % 235U in light water reactors. This publication is the outcome of two technical meetings and compiles the results and conclusions in terms of benefits to be obtained from the use of high assay low enriched uranium (HALEU) fuel, with due consideration of safety issues that arise from its use. It details technological options and corresponding issues regarding fuel and core design, safety analysis and assessments relevant to manufacturing, handling, transportation, storage, irradiation, and performance in normal and accident conditions.

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201109200
Category : Technology & Engineering
Languages : en
Pages : 56

Get Book Here

Book Description
The limitation of 235U enrichment is a current concern among IAEA Member States. In response, work has been undertaken to provide a platform to facilitate a comprehensive review of the current status, prospects and challenges associated with the use of fuels having enrichments higher than 5 % 235U in light water reactors. This publication is the outcome of two technical meetings and compiles the results and conclusions in terms of benefits to be obtained from the use of high assay low enriched uranium (HALEU) fuel, with due consideration of safety issues that arise from its use. It details technological options and corresponding issues regarding fuel and core design, safety analysis and assessments relevant to manufacturing, handling, transportation, storage, irradiation, and performance in normal and accident conditions.

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201110206
Category : Light water reactors
Languages : en
Pages : 45

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Book Description


Uranium Enrichment and Nuclear Weapon Proliferation

Uranium Enrichment and Nuclear Weapon Proliferation PDF Author: Allan S. Krass
Publisher: Routledge
ISBN: 100020054X
Category : Political Science
Languages : en
Pages : 325

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Book Description
Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.

Multilateralization of the Nuclear Fuel Cycle

Multilateralization of the Nuclear Fuel Cycle PDF Author: Yury Yudin
Publisher: UN
ISBN:
Category : Business & Economics
Languages : en
Pages : 128

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Book Description
Global energy demands are driving a potential expansion in the use of nuclear energy worldwide. It is estimated that the global nuclear power capacity could double by 2030. This could result in dissemination of sensitive nuclear technologies that present obvious risks of proliferation. Certain international institutional mechanisms for controlling access to sensitive materials, facilities and technologies are needed for dealing with this problem. Over the past few years, 12 proposals have been put forward by states, nuclear industry and international organizations, aimed at checking the spread of uranium enrichment and spent fuel reprocessing technologies. This book presents an overview and analysis of these proposals, including an evaluation of the projected international mechanisms.

Fuel Modelling in Accident Conditions

Fuel Modelling in Accident Conditions PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201639196
Category : Technology & Engineering
Languages : en
Pages : 180

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Book Description
This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.

Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors

Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201157201
Category : Technology & Engineering
Languages : en
Pages : 144

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Book Description
This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research

TECHNICAL REVIEW OF ACCEPTANCE CRITERIA FOR PRESSURIZED HEAVY WATER REACTOR FUEL.

TECHNICAL REVIEW OF ACCEPTANCE CRITERIA FOR PRESSURIZED HEAVY WATER REACTOR FUEL. PDF Author: IAEA.
Publisher:
ISBN: 9789201168207
Category :
Languages : en
Pages :

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Book Description


Thorium Fuel Cycle

Thorium Fuel Cycle PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 120

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Book Description
Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.

Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5

Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201043191
Category : Business & Economics
Languages : en
Pages : 65

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Book Description
This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF 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.