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Author: Guido Renda
Publisher:
ISBN: 9789279446498
Category :
Languages : en
Pages : 24
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Book Description
The collaborative project for a European Sodium Fast Reactor (CP-ESFR) is an international project where 25 European partners developed Research & Development solutions and concepts for a European sodium fast reactor. The project was funded by the 7th European Union Framework Programme and covered topics such as the reactor architectures and components, the fuel, the fuel element and the fuel cycle, and the safety concepts. Within sub-project 3, dedicated to safety, a task addressed proliferation resistance considerations. The Generation IV International Forum (GIF) Proliferation Resistance & Physical Protection (PR&PP) Evaluation Methodology has been selected as the general framework for this work, complemented by punctual aspects of the IAEA-INPRO Proliferation Resistance methodology and other literature studies - in particular for material type characterization. The activity has been carried out taking the GIF PR&PP Evaluation Methodology and its Addendum as the general guideline for identifying potential nuclear material diversion targets. The targets proliferation attractiveness has been analyzed in terms of the suitability of the targets' nuclear material as the basis for its use in nuclear explosives. To this aim the PR&PP Fissile Material Type measure was supplemented by other literature studies, whose related metrics have been applied to the nuclear material items present in the considered core alternatives. This report will firstly summarize the main ESFR design aspects relevant for PR along the lines of the GIF PR&PP White Paper template. An analysis on proliferation targets is then discussed, with emphasis on their characterization from a nuclear material point of view. Finally, a high-level ESFR PR analysis according to the four main proliferation strategies identified by the GIF PR&PP Evaluation Methodology (concealed diversion, concealed misuse, breakout, clandestine production in clandestine facilities) is presented.
Author: Guido Renda
Publisher:
ISBN: 9789279446498
Category :
Languages : en
Pages : 24
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Book Description
The collaborative project for a European Sodium Fast Reactor (CP-ESFR) is an international project where 25 European partners developed Research & Development solutions and concepts for a European sodium fast reactor. The project was funded by the 7th European Union Framework Programme and covered topics such as the reactor architectures and components, the fuel, the fuel element and the fuel cycle, and the safety concepts. Within sub-project 3, dedicated to safety, a task addressed proliferation resistance considerations. The Generation IV International Forum (GIF) Proliferation Resistance & Physical Protection (PR&PP) Evaluation Methodology has been selected as the general framework for this work, complemented by punctual aspects of the IAEA-INPRO Proliferation Resistance methodology and other literature studies - in particular for material type characterization. The activity has been carried out taking the GIF PR&PP Evaluation Methodology and its Addendum as the general guideline for identifying potential nuclear material diversion targets. The targets proliferation attractiveness has been analyzed in terms of the suitability of the targets' nuclear material as the basis for its use in nuclear explosives. To this aim the PR&PP Fissile Material Type measure was supplemented by other literature studies, whose related metrics have been applied to the nuclear material items present in the considered core alternatives. This report will firstly summarize the main ESFR design aspects relevant for PR along the lines of the GIF PR&PP White Paper template. An analysis on proliferation targets is then discussed, with emphasis on their characterization from a nuclear material point of view. Finally, a high-level ESFR PR analysis according to the four main proliferation strategies identified by the GIF PR&PP Evaluation Methodology (concealed diversion, concealed misuse, breakout, clandestine production in clandestine facilities) is presented.
Author:
Publisher:
ISBN: 9789279446481
Category :
Languages : en
Pages : 24
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Book Description
The collaborative project for a European Sodium Fast Reactor (CP-ESFR) is an international project where 25 European partners developed Research & Development solutions and concepts for a European sodium fast reactor. The project was funded by the 7th European Union Framework Programme and covered topics such as the reactor architectures and components, the fuel, the fuel element and the fuel cycle, and the safety concepts. Within sub-project 3, dedicated to safety, a task addressed proliferation resistance considerations. The Generation IV International Forum (GIF) Proliferation Resistance & Physical Protection (PR & PP) Evaluation Methodology has been selected as the general framework for this work, complemented by punctual aspects of the IAEA-INPRO Proliferation Resistance methodology and other literature studies - in particular for material type characterization. The activity has been carried out taking the GIF PR & PP Evaluation Methodology and its Addendum as the general guideline for identifying potential nuclear material diversion targets. The targets proliferation attractiveness has been analyzed in terms of the suitability of the targets' nuclear material as the basis for its use in nuclear explosives. To this aim the PR & PP Fissile Material Type measure was supplemented by other literature studies, whose related metrics have been applied to the nuclear material items present in the considered core alternatives. This report will firstly summarize the main ESFR design aspects relevant for PR along the lines of the GIF PR & PP White Paper template. An analysis on proliferation targets is then discussed, with emphasis on their characterization from a nuclear material point of view. Finally, a high-level ESFR PR analysis according to the four main proliferation strategies identified by the GIF PR & PP Evaluation Methodology (concealed diversion, concealed misuse, breakout, clandestine production in clandestine facilities) is presented.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
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Book Description
The Integral Fast Reactor (IFR) concept includes a sodium-cooled fast reactor collocated with an integrated pyroprocess fuel recycling facility. The pyrochemical processes and the inert atmosphere of the heavily shielded fuel cycle facility provide inherent proliferation-resistant features for this advanced technology. The reactor can be designed to operate with a number of different conversion factors, so that it could be used for excess plutonium consumption or as a breeder if needed for rapid expansion of energy supply. The system contains a large quantity of plutonium and minor actinides, which at all times remain in extremely hostile environments and in chemical and physical forms that would require additional processing to extract weapons-suitable material. The aqueous processing equipment and facilities to accomplish such separation would not be available on site. Transportation would not be required in the reference deployment scenario. Nevertheless, the proliferation-resistance of some parts of the system could be considerably strengthened by advanced safeguards technologies. In spite of its inherent features, international deployment of the system would probably be limited to stable countries with a strong existing nuclear infrastructure.
Author: North American Aviation. Atomics International Division
Publisher:
ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages : 82
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Book Description
Author: Igor Pioro
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112
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Book Description
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors Includes new trends and developments since the first publication, as well as brand new case studies and appendices Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Author: Lillian Marie Cronholm
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
International Atomic Energy Agency (IAEA) safeguards are one method of proliferation resistance which is applied at most nuclear facilities worldwide. IAEA safeguards act to prevent the diversion of nuclear materials from a facility through the deterrence of detection. However, even with IAEA safeguards present at a facility, the country where the facility is located may still attempt to proliferate nuclear material by exploiting weaknesses in the safeguards system. The IAEA's mission is to detect the diversion of nuclear materials as soon as possible and ideally before it can be weaponized. Modern IAEA safeguards utilize unattended monitoring systems (UMS) to perform nuclear material accountancy and maintain the continuity of knowledge with regards to the position of nuclear material at a facility. This research focuses on evaluating the reliability of unattended monitoring systems and integrating the probabilistic failure of these systems into the comprehensive probabilistic proliferation resistance model of a facility. To accomplish this, this research applies reliability engineering analysis methods to probabilistic proliferation resistance modeling. This approach is demonstrated through the analysis of a safeguards design for the Example Sodium Fast Reactor Fuel Cycle Facility (ESFR FCF). The ESFR FCF UMS were analyzed to demonstrate the analysis and design processes that an analyst or designer would go through when evaluating/designing the proliferation resistance component of a safeguards system. When comparing the mean time to failure (MTTF) for the system without redundancies versus one with redundancies, it is apparent that redundancies are necessary to achieve a design without routine failures. A reliability engineering approach to probabilistic safeguards system analysis and design can be used to reach meaningful conclusions regarding the proliferation resistance of a UMS. The methods developed in this research provide analysts and designers alike a process to follow to evaluate the reliability of a UMS.
Author:
Publisher:
ISBN: 9789279111280
Category :
Languages : en
Pages : 68
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Book Description
This report summarises the different stages and the characteristics of the EISOFAR project. It clarifies the high-level objectives (requirements) assigned to the future European sodium fast reactor (ESFR) and identifies the associated technological viability and performance issues. Proposals are listed for a research and development plan that is necessary to solve these issues. The identified programme has to allow selecting promising options by the end of 2009, then to choose among them, by 2012, those susceptible to optimise the meeting of the objectives. As many as possible of these options will be represented in a prototype which could be deployed from 2020. The vision presented in the document aims to be exhaustive. In a second time it is foreseen that a critical analysis of what is realised at the international level will be achieved to identify the possible complementarities with the current programmes (e.g. generation-IV SFR; national programmes) and to select the actions that can represent an original European contribution, while avoiding duplications. In what follows, and in the light of the contributions from the EISOFAR work packages (WP), it is suggested to tentatively resume and structure the whole activity into four big domains: - Core, fuels, fuel elements and fuel cycles, - Safety, including consideration of severe accidents, - Energy conversion systems and materials, - Simplification and optimisation of the reactor, systems and plant operation. A preliminary indication of the needs, in terms of experimental support, is proposed coherently with the technical programme. The estimation of the average human effort has to be the object of a detailed analysis which will integrate in particular the degree of complementarity which it will be possible to implement at the international level.
Author: Mohit Singh (S.M.)
Publisher:
ISBN:
Category :
Languages : en
Pages : 79
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Book Description
Due to perceived proliferation risks, current US fast reactor designs have avoided the use of uranium blankets. While reducing the amount of plutonium produced, this omission also restrains the reactor design space and has several disadvantages over blanketed cores. This study investigated many blanket options that would satisfy the proliferation concern while minimizing negative fuel cycle impact. To do so, a multi-variable metric was developed that combines 6 attributes: proliferation resistance, fuel fabrication, radiotoxicity, breeding gain, reactivity penalty and transportation. The final version of the metric consisted of using a yes or no decision on the proliferation criteria proposed by Bathke (for technologically advanced nations). The remaining 5 attributes are scaled between 0 and 1 with assigned weights for each. For our analysis, a 2400MWth sodium cooled core was considered. One row of blanket was added radially. Metal fuel composed of depleted uranium, zirconium and Np/Pu from light water reactor used fuel was used for the driver. It was determined that to meet the prescribed proliferation resistance criteria, a minimum of 4% MA (by volume) was needed in the blanket assemblies. However, increasing the amount of MA past 4% became detrimental to the combination of the other 5 attributes, mainly impacting the radiotoxicity, fuel fabrication and transportation. The addition of moderation by itself did not provide any means of dissipating proliferation issues. In the cases studied, it was determined that ZrH1.6 and BeO were the most promising moderating materials. They both provided some reduction in required MA concentration but at the expense of the radiotoxicity of the end product. Using our defined metric, it was determined that moderation provided no immediate benefit. It should also be noted that the homogeneous or heterogeneous addition of moderators has minimal impact on such scoping studies. Separation of the Cm/Bk/Cf vector from the Am was also studied. The blankets were composed of Am while the remaining Cm/Bk/Cf was left to decay in storage. The metric was then applied to the combined streams for all attributes except proliferation. The separated case performed worst in all cases examined. Also, as expected, varying the uranium composition vector from natural (NU), depleted (DU) and recycled (RU) had very little impact on our metric, thus the choice of uranium vector would be mostly left to cost and initial fabrication considerations. It should however be noted that the k-infinity at beginning-of-life was obviously higher for the recycled and natural cases. Looking at the reactivity over the first cycle indicates that NU provides an additional -40pcm over DU while RU provides -60pcm, which could provide 30 and 45 extra days of operation, respectively, or a reduction in driver core enrichment for a given cycle length.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
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Book Description
Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.
Author: Richard Royce Madison Metcalf
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The comparison of nuclear facilities based on their barriers to nuclear material proliferation has remained a difficult endeavor, often requiring expert elicitation for each system under consideration. However, objectively comparing systems using a set of computable metrics to derive a single number representing a system is not, in essence, a nuclear nonproliferation specific problem and significant research has been performed for business models. For instance, Multi-Attribute Utility Analysis (MAUA) methods have been used previously to provide an objective insight of the barriers to proliferation. In this paper, the Proliferation Resistance Analysis and Evaluation Tool for Observed Risk (PRAETOR), a multi-tiered analysis tool based on the multiplicative MAUA method, is presented. It folds sixty three mostly independent metrics over three levels of detail to give an ultimate metric for nonproliferation performance comparison. In order to reduce analysts' bias, the weighting between the various metrics was obtained by surveying a total of thirty three nonproliferation specialists and nonspecialists from fields such as particle physics, international policy, and industrial engineering. The PRAETOR was used to evaluate the Fast Breeder Reactor Fuel Cycle (FBRFC). The results obtained using these weights are compared against a uniform weight approach. Results are presented for five nuclear material diversion scenarios: four examples include a diversion attempt on various components of a PUREX fast reactor cycle and one scenario involves theft from a PUREX facility in a LWR cycle. The FBRFC was evaluated with uranium-plutonium fuel and a second time using thorium-uranium fuel. These diversion scenarios were tested with both uniform and expert weights, with and without safeguards in place. The numerical results corroborate nonproliferation truths and provide insight regarding fast reactor facilities' proliferation resistance in relation to known standards.
