Investigation Of Natural Circulation Instability And Transients In Passively Safe Small Modular Reactors

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Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors

Author :
Publisher :
ISBN 13 :
Total Pages : 267 pages
Book Rating : 4.:/5 (982 download)

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Book Synopsis Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors by :

Download or read book Investigation of Natural Circulation Instability and Transients in Passively Safe Small Modular Reactors written by and published by . This book was released on 2016 with total page 267 pages. Available in PDF, EPUB and Kindle. Book excerpt: The NEUP funded project, NEUP-3496, aims to experimentally investigate two-phase natural circulation flow instability that could occur in Small Modular Reactors (SMRs), especially for natural circulation SMRs. The objective has been achieved by systematically performing tests to study the general natural circulation instability characteristics and the natural circulation behavior under start-up or design basis accident conditions. Experimental data sets highlighting the effect of void reactivity feedback as well as the effect of power ramp-up rate and system pressure have been used to develop a comprehensive stability map. The safety analysis code, RELAP5, has been used to evaluate experimental results and models. Improvements to the constitutive relations for flashing have been made in order to develop a reliable analysis tool. This research has been focusing on two generic SMR designs, i.e. a small modular Simplified Boiling Water Reactor (SBWR) like design and a small integral Pressurized Water Reactor (PWR) like design. A BWR-type natural circulation test facility was firstly built based on the three-level scaling analysis of the Purdue Novel Modular Reactor (NMR) with an electric output of 50 MWe, namely NMR-50, which represents a BWR-type SMR with a significantly reduced reactor pressure vessel (RPV) height. The experimental facility was installed with various equipment to measure thermalhydraulic parameters such as pressure, temperature, mass flow rate and void fraction. Characterization tests were performed before the startup transient tests and quasi-steady tests to determine the loop flow resistance. The control system and data acquisition system were programmed with LabVIEW to realize the realtime control and data storage. The thermal-hydraulic and nuclear coupled startup transients were performed to investigate the flow instabilities at low pressure and low power conditions for NMR-50. Two different power ramps were chosen to study the effect of startup power density on the flow instability. The experimental startup transient results showed the existence of three different flow instability mechanisms, i.e., flashing instability, condensation induced flow instability, and density wave oscillations. In addition, the void-reactivity feedback did not have significant effects on the flow instability during the startup transients for NMR-50. ii Several initial startup procedures with different power ramp rates were experimentally investigated to eliminate the flow instabilities observed from the startup transients. Particularly, the very slow startup transient and pressurized startup transient tests were performed and compared. It was found that the very slow startup transients by applying very small power density can eliminate the flashing oscillations in the single-phase natural circulation and stabilize the flow oscillations in the phase of net vapor generation. The initially pressurized startup procedure was tested to eliminate the flashing instability during the startup transients as well. The pressurized startup procedure included the initial pressurization, heat-up, and venting process. The startup transient tests showed that the pressurized startup procedure could eliminate the flow instability during the transition from single-phase flow to two-phase flow at low pressure conditions. The experimental results indicated that both startup procedures were applicable to the initial startup of NMR. However, the pressurized startup procedures might be preferred due to short operating hours required. In order to have a deeper understanding of natural circulation flow instability, the quasi-steady tests were performed using the test facility installed with preheater and subcooler. The effect of system pressure, core inlet subcooling, core power density, inlet flow resistance coefficient, and void reactivity feedback were investigated in the quasi-steady state tests. The experimental stability boundaries were determined ...

Experimental Investigations of Natural Circulation in a Separate-and-mixed Effects Test Facility Mimicking Prismatic Modular Reactor (PMR) Core

Download Experimental Investigations of Natural Circulation in a Separate-and-mixed Effects Test Facility Mimicking Prismatic Modular Reactor (PMR) Core PDF Online Free

Author : Mahmoud M. Taha
Publisher :
ISBN 13 :
Total Pages : 207 pages
Book Rating : 4.:/5 (12 download)

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Book Synopsis Experimental Investigations of Natural Circulation in a Separate-and-mixed Effects Test Facility Mimicking Prismatic Modular Reactor (PMR) Core by : Mahmoud M. Taha

Download or read book Experimental Investigations of Natural Circulation in a Separate-and-mixed Effects Test Facility Mimicking Prismatic Modular Reactor (PMR) Core written by Mahmoud M. Taha and published by . This book was released on 2017 with total page 207 pages. Available in PDF, EPUB and Kindle. Book excerpt: "After the Fukushima Daiichi nuclear power plant accident in 2011, significant attention was directed to investigate natural circulation thermal-hydraulics in Prismatic Modular Reactors (PMRs). Natural circulation is employed as a passive safety feature that passively removes the decay heat released after the loss of flow accidents (LOFA). Several computational studies have addressed such phenomena, however, validation of Computational Fluid Dynamics (CFD) is needed by providing high-quality data obtained from separate test facilities designed with reference to the corresponding reference PMRs. To address this need, a separate effects Plenum-to-Plenum Facility (P2PF) was designed and developed with dual channels and plena for experimental investigations of naturally driven gas thermal and velocity fields under different circulation intensities. Thermal and velocity measurements have been characterized by implementation of advanced sophisticated measurement techniques such as: (1) the hot wire anemometry (HWA), (2) flush-mounted micro-foil sensors, and (3) thermocouples that are capable of providing local measurements at different axial and radials positions along both channels. These measurement techniques have been integrated in a novel way so that the thermocouple readings are not disturbed by the HWA sensor, and vice versa. This proposed work has a significant impact on advancing the knowledge and understanding of the plenum-to-plenum (P2P) natural circulation thermal-hydraulic phenomenon and provides high-quality benchmark data that are much needed for verification and validation (V & V) of computational fluid dynamics (CFD) models and codes. Therefore, computational simulations can be reliably used in designing PMRs passive safety systems and in safety analysis and assessment"--Abstract, page iv.

An Analytical and Experimental Investigation of Natural Circulation Transients in a Model Pressurized Water Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis An Analytical and Experimental Investigation of Natural Circulation Transients in a Model Pressurized Water Reactor by :

Download or read book An Analytical and Experimental Investigation of Natural Circulation Transients in a Model Pressurized Water Reactor written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Natural Circulation phenomena in a simulated PWR was investigated experimentally and analytically. The experimental investigation included determination of system characteristics as well as system response to the imposed transient under symmetric and asymmetric operations. System characteristics were used to obtain correlation for heat transfer coefficient in heat exchangers, system flow resistance, and system buoyancy heat. Asymmetric transients were imposed to study flow oscillation and possible instability. The analytical investigation encompassed development of mathematical model for single-phase, steady-state and transient natural circulation as well as modification of existing model for two-phase flow analysis of phenomena such as small break LOCA, high pressure coolant injection and pump coast down. The developed mathematical model for single-phase analysis was computer coded to simulate the imposed transients. The computer program, entitled ''Symmetric and Asymmetric Analysis of Single-Phase Flow (SAS), '' were employed to simulate the imposed transients. It closely emulated the system behavior throughout the transient and subsequent steady-state. Modifications for two-phase flow analysis included addition of models for once-through steam generator and electric heater rods. Both programs are faster than real time. Off-line, they can be used for prediction and training applications while on-line they serve for simulation and signal validation. The programs can also be used to determine the sensitivity of natural circulation behavior to variation of inputs such as secondary distribution and power transients.

Anticipated and Abnormal Plant Transients in Light Water Reactors

Author : Pamela Lassahn
Publisher : Springer Science & Business Media
ISBN 13 : 1468447998
Total Pages : 725 pages
Book Rating : 4.4/5 (684 download)

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Book Synopsis Anticipated and Abnormal Plant Transients in Light Water Reactors by : Pamela Lassahn

Download or read book Anticipated and Abnormal Plant Transients in Light Water Reactors written by Pamela Lassahn and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 725 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the last 30 years, reactor safety technology has evolved not so much from a need to recover from accidents or incidents, but primarily from many groups in the nuclear community asking hypo thetical, searching (what if) ~uestions. This ~uestioning has indeed paid off in establishing preventive measures for many types of events and potential accidents. Conditions, such as reactivity excursions, large break, loss of coolant, core melt, and contain ment integrity loss, to name a few, were all at one time topics of protracted discussions on hypothesized events. Historically, many of these have become multiyear, large-scale research programs aimed at resolving the "what ifs. " For the topic of anticipated and abnormal plant transients, how ever, the searching ~uestions and the research were not so prolific until the mid-1970s. At that time, probabilistic risk methodolo gies began to tell us we should change our emphasis in reactor safety research and development and focus more on small pipe breaks and plant transients. Three Mile Island punctuated that message in 1979. The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant.

An Analytical and Experimental Investigation of Natural Circulation Transients in a Model Pressurized Water Reactor

Author : Mahmoud Massoud
Publisher :
ISBN 13 :
Total Pages : 246 pages
Book Rating : 4.:/5 (158 download)

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Book Synopsis An Analytical and Experimental Investigation of Natural Circulation Transients in a Model Pressurized Water Reactor by : Mahmoud Massoud

Download or read book An Analytical and Experimental Investigation of Natural Circulation Transients in a Model Pressurized Water Reactor written by Mahmoud Massoud and published by . This book was released on 1987 with total page 246 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors

Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9789201274106
Total Pages : 423 pages
Book Rating : 4.2/5 (741 download)

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Book Synopsis Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors by : International Atomic Energy Agency

Download or read book Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 423 pages. Available in PDF, EPUB and Kindle. Book excerpt: Based on an IAEA coordinated research project focused on the use of passive safety systems and natural circulation to help meet the safety and economic goals of advanced nuclear power plants, this publication includes the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems, characterization of each phenomenon, integral tests to examine the passive systems and natural circulation, and a methodology for examining passive system reliability.

Natural Circulation in Water Cooled Nuclear Power Plants

Author : International Atomic Energy Agency
Publisher : IAEA
ISBN 13 :
Total Pages : 656 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Natural Circulation in Water Cooled Nuclear Power Plants by : International Atomic Energy Agency

Download or read book Natural Circulation in Water Cooled Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 656 pages. Available in PDF, EPUB and Kindle. Book excerpt: Describes the state of knowledge of natural circulation in water cooled nuclear power plants and passive system reliability. The publication presents information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.

Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

Author : Dongyoung Lee
Publisher :
ISBN 13 :
Total Pages : 132 pages
Book Rating : 4.:/5 (914 download)

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Book Synopsis Flow Dynamics and Condensation of Film Flows in Small Modular Reactors by : Dongyoung Lee

Download or read book Flow Dynamics and Condensation of Film Flows in Small Modular Reactors written by Dongyoung Lee and published by . This book was released on 2015 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt: There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive and natural circulation forces under normal operations and accident conditions. One key feature of the safety systems in SMRs is the use of containment condensation to prevent core melt down. For further development of the SMR for design certifications, the condensation model at relatively high pressures compared with current operating power plants should be verified and validated. For this process, at Oregon State University, the MASLWR (Multi Application Small Light Water Reactor) test facility, which has 1:3 length scale, can perform integrated tests on containment condensation of SMRs. Using the MASLWR test facility experimental data, this study investigated three major subjects: heat flux estimation on the containment wall, flow transition of condensation film flow dynamics and assessing the scaling effects of the MASLWR test facility. An inverse heat conduction algorithm was developed to estimate the heat fluxes of film condensation at the containment wall in the MASLWR test facility during transients. Through a fundamental one-dimensional approach for condensation film flow, the governing equations were derived and numerically solved. A linear perturbation stability analysis using steady-state results of condensation film flow at the containment wall found that Re ~1600 is the transition point between laminar and turbulent film flow regimes. This finding agreed with the experimental results of Ishigai et al. (1974) and Morioka et al. (1993). Based on scaling analysis using the diffusion layer model and experimental correlations, the length distortion factor was examined. In this study, it was found that the 1:3 length scale test facility underestimated the heat transfer rate more than the prototype. The results presented in this dissertation cover the film flow dynamics of condensation film flows as well as an inverse heat transfer calculation to advance the knowledge of containment condensation in SMRs.

Single-phase, Two-phase and Supercritical Natural Circulation Systems

Author : Pallippattu Krishnan Vijayan
Publisher : Woodhead Publishing
ISBN 13 : 0081024878
Total Pages : 650 pages
Book Rating : 4.0/5 (81 download)

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Book Synopsis Single-phase, Two-phase and Supercritical Natural Circulation Systems by : Pallippattu Krishnan Vijayan

Download or read book Single-phase, Two-phase and Supercritical Natural Circulation Systems written by Pallippattu Krishnan Vijayan and published by Woodhead Publishing. This book was released on 2019-06-19 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt: Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation systems. This book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and parallel channel systems. Each chapter begins with an introduction to the circulation system before discussing each element in detail and analyzing its effect on the performance of the system. The book also presents thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike. This book is invaluable for engineers, designers, operators and consultants in nuclear, mechanical, electrical and chemical disciplines. Presents single-phase, two-phase and supercritical natural circulation systems together in one resource to fill an existing knowledge gap Guides the reader through relevant processes, such as designing, analyzing and generating stability maps and natural circulation loops, calculating heat transport capabilities, and maintaining natural circulation system operations Includes global case studies and examples to increase understanding, along with important IAEA standards and procedures

Handbook of Small Modular Nuclear Reactors

Author : Daniel T. Ingersoll
Publisher : Woodhead Publishing
ISBN 13 : 0128239174
Total Pages : 648 pages
Book Rating : 4.1/5 (282 download)

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Book Synopsis Handbook of Small Modular Nuclear Reactors by : Daniel T. Ingersoll

Download or read book Handbook of Small Modular Nuclear Reactors written by Daniel T. Ingersoll and published by Woodhead Publishing. This book was released on 2020-10-22 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook of Small Modular Nuclear Reactors, Second Edition is a fully updated comprehensive reference on Small Modular Reactors (SMRs), which reflects the latest research and technological advances in the field from the last five years. Editors Daniel T. Ingersoll and Mario D. Carelli, along with their team of expert contributors, combine their wealth of collective experience to update this comprehensive handbook that provides the reader with all required knowledge on SMRs, expanding on the rapidly growing interest and development of SMRs around the globe. This book begins with an introduction to SMRs for power generation, an overview of international developments, and an analysis of Integral Pressurized Water Reactors as a popular class of SMRs. The second part of the book is dedicated to SMR technologies, including physics, components, I&C, human-system interfaces and safety aspects. Part three discusses the implementation of SMRs, covering economic factors, construction methods, hybrid energy systems and licensing considerations. The fourth part of the book provides an in-depth analysis of SMR R&D and deployment of SMRs within eight countries, including the United States, Republic of Korea, Russia, China, Argentina, and Japan. This edition includes brand new content on the United Kingdom and Canada, where interests in SMRs have increased considerably since the first edition was published. The final part of the book adds a new analysis of the global SMR market and concludes with a perspective on SMR benefits to developing economies. This authoritative and practical handbook benefits engineers, designers, operators, and regulators working in nuclear energy, as well as academics and graduate students researching nuclear reactor technologies. Presents the latest research on SMR technologies and global developments Includes new case study chapters on the United Kingdom and Canada and a chapter on global SMR markets Discusses new technologies such as floating SMRs and molten salt SMRs

Super Light Water Reactors and Super Fast Reactors

Author : Yoshiaki Oka
Publisher : Springer Science & Business Media
ISBN 13 : 1441960341
Total Pages : 664 pages
Book Rating : 4.4/5 (419 download)

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Book Synopsis Super Light Water Reactors and Super Fast Reactors by : Yoshiaki Oka

Download or read book Super Light Water Reactors and Super Fast Reactors written by Yoshiaki Oka and published by Springer Science & Business Media. This book was released on 2010-07-01 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt: Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.

A Theoretical Study of the Transient Operation and Stability of Two-phase Natural Circulation Loops

Author : Kermit Garlid
Publisher :
ISBN 13 :
Total Pages : 90 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis A Theoretical Study of the Transient Operation and Stability of Two-phase Natural Circulation Loops by : Kermit Garlid

Download or read book A Theoretical Study of the Transient Operation and Stability of Two-phase Natural Circulation Loops written by Kermit Garlid and published by . This book was released on 1961 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt: Mathematical models of the time-dependent behavior of two-phase natural-circulation loops were used to predict the operation and to explain the unusual instability sometimes observed. The initial results obtained for a loop similar to the Univ. of Minnesota loop were used to formulate a more complex and accurate model, and the predicted transient behavior was in close agreement with the experimental results from the Minnesota loop. For a 300 psia, high-pressure loop, unstable oscillatory behavior was predicted under certain conditions and stable behavior under others. Closed unstable regions rather than limits were predicted, and the specifications of stability in terms of a single parameter were found to be impossible. The great difference in oscillatory frequencies observed at low and high pressures was found to be due largely to the system geometry. The criterion for the absence of oscillations was found to be similar to one of the criteria for stability of chemical reaction systems.

Transient Analysis of Two-phase Natural-circulation Systems

Author : R. P. Anderson
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Transient Analysis of Two-phase Natural-circulation Systems by : R. P. Anderson

Download or read book Transient Analysis of Two-phase Natural-circulation Systems written by R. P. Anderson and published by . This book was released on 1962 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents a technique for solving the equations of a natural-circulation system. The solutions are compared with experimental results at various pressures with two geometries in boiling water systems.

Thermal-Hydraulics of Water Cooled Nuclear Reactors

Author : Francesco D'Auria
Publisher : Woodhead Publishing
ISBN 13 : 0081006799
Total Pages : 1200 pages
Book Rating : 4.0/5 (81 download)

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Book Synopsis Thermal-Hydraulics of Water Cooled Nuclear Reactors by : Francesco D'Auria

Download or read book Thermal-Hydraulics of Water Cooled Nuclear Reactors written by Francesco D'Auria and published by Woodhead Publishing. This book was released on 2017-05-18 with total page 1200 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Status of Fast Reactor Research and Technology Development

Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9781523130191
Total Pages : 0 pages
Book Rating : 4.1/5 (31 download)

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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.

Progress in Methodologies for the Assessment of Passive Safety System Reliability in Advanced Reactors

Author : International Atomic Energy Agency
Publisher : IAEA Tecdoc
ISBN 13 : 9789201086143
Total Pages : 223 pages
Book Rating : 4.0/5 (861 download)

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Book Synopsis Progress in Methodologies for the Assessment of Passive Safety System Reliability in Advanced Reactors by : International Atomic Energy Agency

Download or read book Progress in Methodologies for the Assessment of Passive Safety System Reliability in Advanced Reactors written by International Atomic Energy Agency and published by IAEA Tecdoc. This book was released on 2014-09 with total page 223 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication summarizes the results of an IAEA coordinated research project on the development of advanced methodologies for the assessment of passive safety system performance in advanced reactors. This includes discussions on various methodologies to assess the performance of passive engineered safety features in innovative small reactors, including the Indian AHWR 300 LEU and the Argentinian CAREM25. The publication focuses on the different reliability assessment approaches, methodologies, analysis and evaluation of the results and technical challenges. It provides the insights resulting from the analysis on the technical issues associated with assessing the reliability of passive systems in the context of nuclear safety and probabilistic safety analysis. A viable path towards the implementation of the research efforts in the related areas is also delineated.

Experimental and analytical study of stability characteristics of natural circulation boiling water reactors during startup transient : thesis

Download Experimental and analytical study of stability characteristics of natural circulation boiling water reactors during startup transient : thesis PDF Online Free

Author : Kyoungsuk Woo
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)

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Book Synopsis Experimental and analytical study of stability characteristics of natural circulation boiling water reactors during startup transient : thesis by : Kyoungsuk Woo

Download or read book Experimental and analytical study of stability characteristics of natural circulation boiling water reactors during startup transient : thesis written by Kyoungsuk Woo and published by . This book was released on 2008 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: