Safeguards Techniques and Equipment

Safeguards Techniques and Equipment
Author: International Atomic Energy Agency
Publisher:
Total Pages: 146
Release: 2011
Genre: Environmental sampling
ISBN: 9789201189103

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The 1990s saw significant developments in the global non-proliferation landscape, resulting in a new period of safeguards development. The current publication, which is the second revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the safeguards techniques and equipment used for nuclear material accountancy, containment and surveillance measures, environmental sampling, and data security. New features include a section on new and novel technologies. As new verification measures continue to be developed, the material in this book will be reviewed periodically and updated versions issued.

Safeguards Considerations in the Study of Proliferation Resistance of Plutonium Disposition Options

Safeguards Considerations in the Study of Proliferation Resistance of Plutonium Disposition Options
Author:
Publisher:
Total Pages: 9
Release: 1997
Genre:
ISBN:

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Domestic and international safeguards considerations of the various plutonium disposition program options were studied. The options included immobilization in either glass or ceramic; deep borehole disposal, either directly as oxide or after immobilization in ceramic pellets; and nine options of burning in reactors as mixed oxide (MOX) fuel. Two of the MOX options considered burning in CANDU (Canadian deuterium uranium) reactors in Canada; the remaining options used either existing or new reactors in the US. A facility for conversion of weapons-grade PU metal to plutonium oxide is common to all options. Although domestic safeguards are applied for all material in the facility, international verification probably will not be possible until weapons design information from material form can no longer be inferred. Assuming that the facility processed 5 tonnes of Pu/year and all measurements are made to meet 1993 ESARDA (European Safeguards Research and Development Association) Target Values, the best annual detection limit (false alarm probability = 0.05, detection probability = 0.95) for loss of Pu can be no smaller than 16.5 kg, and probably will be higher. A MOX fuel fabrication facility is required for all of the reactor options, and location of the facility either in the US or in a EURATOM country was considered. Assuming that the facility processes 3.2 tonnes of Pu/year, and all measurements are made to meet ESARDA Target Values, the best annual detection limit for loss of Pu can be no smaller than 24 kg. Location in Europe adds an additional international safeguards burden. Impact of the various disposal options on domestic and international safeguards will be reviewed.

International Safeguards in the Design of Nuclear Reactors

International Safeguards in the Design of Nuclear Reactors
Author: International Atomic Energy Agency
Publisher:
Total Pages: 0
Release: 2014
Genre: Science
ISBN: 9789201065148

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This publication is the second in the IAEA Nuclear Energy Series to provide guidance on the inclusion of safeguards in nuclear facility design and construction. It is principally intended for designers and operators of nuclear reactor facilities; however, vendors, national authorities and financial backers can also benefit from the information provided. It is introductory rather than comprehensive in nature, complementing the Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols, IAEA Services Series No. 21, and other publications in that series. The publication complements the general considerations addressed in International Safeguards in Nuclear Facility Design and Construction, IAEA Nuclear Energy Series No. NP-T-2.8.

Impact of Certain Safeguards Considerations on Fuel-cycle Facility Design

Impact of Certain Safeguards Considerations on Fuel-cycle Facility Design
Author:
Publisher:
Total Pages:
Release: 1979
Genre:
ISBN:

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Both physical protection and containment/surveillance systems impact plant design and operations. Effective physical protection systems can be systematically designed; work on designing containment/surveillance systems is in progress. Fuel fabrication facility designers need to be cognizant of these safeguards system developments to enable effective implementation of them with as little effect on plant functions as possible. This brief overview provides a general indication of what the impacts of the systems might be, and current thinking on their structure.

Design of an Engineered Safeguards System for a Mixed-oxide Fuel Fabrication Facility

Design of an Engineered Safeguards System for a Mixed-oxide Fuel Fabrication Facility
Author:
Publisher:
Total Pages:
Release: 1977
Genre:
ISBN:

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Several Engineered Safeguards System concepts and designs are described that provide increased protection against a wide spectrum of adversary threats. An adversary sequence diagram that outlines all possible adversary paths through the safeguards elements in a mixed-oxide fuel fabrication facility is shown. An example of a critical adversary path is given.

Nuclear Energy Basic Principles

Nuclear Energy Basic Principles
Author: International Atomic Energy Agency
Publisher:
Total Pages: 0
Release: 2008
Genre: Business & Economics
ISBN: 9789201126085

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Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.

Conceptual Design of Integrated Safeguards Systems

Conceptual Design of Integrated Safeguards Systems
Author:
Publisher:
Total Pages:
Release: 1977
Genre:
ISBN:

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The Los Alamos Scientific Laboratory (LASL) is currently involved in the conceptual design of safeguards for generic facilities in the back-end of the nuclear fuel cycle (spent-fuel reprocessing, plutonium nitrate-to-oxide conversion, mixed-oxide fuel fabrication, plutonium scrap recovery, and waste handling). These studies are first steps aimed at eventually providing detailed designs of integrated safeguards systems to guide safeguards-related facility construction and/or modification. The purpose of this presentation is to describe the conceptual design process in terms of its definition, a systematic procedure for its implementation, some of the tools required, and an example of the results of a conceptual design. The value of conceptual design and its relationship to other facets of the complete facility design process are also discussed.

Descriptive Uranium Deposit and Mineral System Models

Descriptive Uranium Deposit and Mineral System Models
Author: International Atomic Energy Agency
Publisher:
Total Pages: 313
Release: 2020-06-30
Genre: Technology & Engineering
ISBN: 9789201092205

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Descriptive Uranium Deposit and Mineral System Models This publication provides a set of systematic descriptive models for each uranium deposit type, subtype and class, using a consistent approach to summarise the same types of information for each. Each model is intended to have a standalone capability, using a tabular style that is typical of conventional mineral resource industry standards. Each deposit model includes a map showing the distribution of deposits, and grade-tonnage graphs. Collectively, these databases and models form a basis for assessing the global distribution of uranium deposits and evaluating supply-demand scenarios. With these, the IAEA can provide the capability for Member States to assess the potential of remaining -- or speculative -- uranium resources for long term supply beyond identified resources in a consistent and reproducible manner.