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Reliability Engineering Approach To Probabilistic Proliferation Resistance Analysis Of The Example Sodium Fast Reactor Fuel Cycle Facility
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Book Synopsis Reliability Engineering Approach to Probabilistic Proliferation Resistance Analysis of the Example Sodium Fast Reactor Fuel Cycle Facility by : Lillian Marie Cronholm
Download or read book Reliability Engineering Approach to Probabilistic Proliferation Resistance Analysis of the Example Sodium Fast Reactor Fuel Cycle Facility written by Lillian Marie Cronholm and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Proliferation Resistance and Material Type Considerations Within the Collaborative Project for a European Sodium Fast Reactor by : Guido Renda
Download or read book Proliferation Resistance and Material Type Considerations Within the Collaborative Project for a European Sodium Fast Reactor written by Guido Renda and published by . This book was released on 2014 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Nuclear Systems Reliability Engineering and Risk Assessment by : Jerry B. Fussell
Download or read book Nuclear Systems Reliability Engineering and Risk Assessment written by Jerry B. Fussell and published by SIAM. This book was released on 1977-01-01 with total page 884 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reliability Improvement with Design of Experiment by : Lloyd Condra
Download or read book Reliability Improvement with Design of Experiment written by Lloyd Condra and published by CRC Press. This book was released on 2018-05-04 with total page 395 pages. Available in PDF, EPUB and Kindle. Book excerpt: A guide to implementing and operating a practical reliability program using carefully designed experiments to provide information quickly, efficiently and cost effectively. It emphasizes real world solutions to daily problems. The second edition contains a special expanded section demonstrating how to combine accelerated testing with design of experiments for immediate improvement.
Book Synopsis Revisions to LA-2735 Fast Reactor Core Test Facility Safety Analysis Report by :
Download or read book Revisions to LA-2735 Fast Reactor Core Test Facility Safety Analysis Report written by and published by . This book was released on 1963 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reliability and Risk Analysis by : Norman J. McCormick
Download or read book Reliability and Risk Analysis written by Norman J. McCormick and published by Academic Press. This book was released on 1981-07-28 with total page 472 pages. Available in PDF, EPUB and Kindle. Book excerpt: A prior knowledge of probability theory would be helpful for the material in Part I; likewise, a previous introduction to the engineered safety features of a nuclear reactor makes portions of Part II easier to understand. For those without this background, introductory material is provided in Chapter 2 and the appendixes.
Book Synopsis MEHODOLOGY FOR PROLIFERATION RESISTANCE FOR ADVANCE NUCLEAR ENERGY SYSTEMS. by : L. Y. CHANG
Download or read book MEHODOLOGY FOR PROLIFERATION RESISTANCE FOR ADVANCE NUCLEAR ENERGY SYSTEMS. written by L. Y. CHANG and published by . This book was released on 2006 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Technology Goals for Generation IV nuclear energy systems highlight Proliferation Resistance and Physical Protection (PR & PP) as one of the four goal areas for Generation 1V nuclear technology. Accordingly, an evaluation methodology is being developed by a PR & PP Experts Group. This paper presents a possible approach, which is based on Markov modeling, to the evaluation methodology for Generation IV nuclear energy systems being developed for PR & PP. Using the Markov model, a variety of proliferation scenarios can be constructed and the proliferation resistance measures can be quantified, particularly the probability of detection. To model the system with increased fidelity, the Markov model is further developed to incorporate multiple safeguards approaches in this paper. The approach to the determination of the associated parameters is presented. Evaluations of diversion scenarios for an example sodium fast reactor (ESFR) energy system are used to illustrate the methodology. The Markov model is particularly useful because it can provide the probability density function of the time it takes for the effort to be detected at a specific stage of the proliferation effort.
Book Synopsis Measurement Control Design and Performance Assessement in the Integral Fast Reactor Fuel Cycle by :
Download or read book Measurement Control Design and Performance Assessement in the Integral Fast Reactor Fuel Cycle written by and published by . This book was released on 1994 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Methods for Quantifying Uncertainty in Fast Reactor Analyses by :
Download or read book Methods for Quantifying Uncertainty in Fast Reactor Analyses written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Liquid-metal-cooled fast reactors in the form of sodium-cooled fast reactors have been successfully built and tested in the U.S. and throughout the world. However, no fast reactor has operated in the U.S. for nearly fourteen years. More importantly, the U.S. has not constructed a fast reactor in nearly 30 years. In addition to reestablishing the necessary industrial infrastructure, the development, testing, and licensing of a new, advanced fast reactor concept will likely require a significant base technology program that will rely more heavily on modeling and simulation than has been done in the past. The ability to quantify uncertainty in modeling and simulations will be an important part of any experimental program and can provide added confidence that established design limits and safety margins are appropriate. In addition, there is an increasing demand from the nuclear industry for best-estimate analysis methods to provide confidence bounds along with their results. The ability to quantify uncertainty will be an important component of modeling that is used to support design, testing, and experimental programs. Three avenues of UQ investigation are proposed. Two relatively new approaches are described which can be directly coupled to simulation codes currently being developed under the Advanced Simulation and Modeling program within the Reactor Campaign. A third approach, based on robust Monte Carlo methods, can be used in conjunction with existing reactor analysis codes as a means of verification and validation of the more detailed approaches.
Book Synopsis Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems by : Friederike Bostelmann
Download or read book Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems written by Friederike Bostelmann and published by . This book was released on 2020 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Mots-clés de l'auteur: sodium-cooled fast reactor ; uncertainty analysis ; sensitivity analysis ; nuclear data ; random sampling ; XSUSA ; SCALE.
Book Synopsis Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors by : AYDIN KARAHAN
Download or read book Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors written by AYDIN KARAHAN and published by . This book was released on 2010-03 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fire Criticality Probability Analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility. Revision 1 by :
Download or read book Fire Criticality Probability Analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility. Revision 1 written by and published by . This book was released on 1995 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Systems Reliability Engineering and Risk Assessment by :
Download or read book Nuclear Systems Reliability Engineering and Risk Assessment written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analysis of Transient Overpower Scenarios in Sodium Fast Reactors by : David Grabaskas
Download or read book Analysis of Transient Overpower Scenarios in Sodium Fast Reactors written by David Grabaskas and published by . This book was released on 2010 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The objective of this research was the demonstration of a methodology to handle epistemic and aleatory uncertainties within an unprotected transient overpower (TOP) scenario in a sodium fast reactor. This study included a comparison of the risk of TOP scenarios to safety limits that are being considered by the U.S. Nuclear Regulatory Commission for future reactor designs. An analysis of the relative importance of uncertainties was also made. The results of this experiment demonstrated that the core damage frequency for an unprotected transient overpower scenario fell well below the proposed safety limits, even without taking credit for the reliability of the reactor protection system. The control rod driveline feedback and Doppler feedback mechanisms were found to be the most important epistemic uncertainties.
Book Synopsis Status of Fast Reactor Research and Technology Development by : International Atomic Energy Agency
Download or read book Status of Fast Reactor Research and Technology Development written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Book Synopsis Thorium Fuel Cycle by : International Atomic Energy Agency
Download or read book Thorium Fuel Cycle written by International Atomic Energy Agency and published by . This book was released on 2005 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors by : International Atomic Energy Agency
Download or read book Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt: The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
