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Evaluation Of Treatment Of Effects Of Debris In Coolant On Eccs And Css Performance In Pressurized Water Reactors And Boiling Water Reactors
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Book Synopsis Evaluation of Treatment of Effects of Debris in Coolant on ECCS and CSS Performance in Pressurized Water Reactors and Boiling Water Reactors by :
Download or read book Evaluation of Treatment of Effects of Debris in Coolant on ECCS and CSS Performance in Pressurized Water Reactors and Boiling Water Reactors written by and published by . This book was released on 2010 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Debris Impact on Emergency Coolant Recirculation by :
Download or read book Debris Impact on Emergency Coolant Recirculation written by and published by OECD Publishing. This book was released on 2004 with total page 430 pages. Available in PDF, EPUB and Kindle. Book excerpt: Under normal operation, nuclear reactor fuel is cooled by water circulating in the primary circuit. In the case of an accident, the reactor is stopped automatically, and residual fuel heat must be evacuated, typically by use of a safety injection system and a reactor containment spray system. This publication contains the proceedings of a workshop, held in New Mexico, United States in February 2004, to discuss recent research and developments to deal with the impact of debris (such as insulating material, concrete particles or paint) on emergency coolant recirculation systems.
Book Synopsis Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance by : D. V. Rao
Download or read book Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance written by D. V. Rao and published by . This book was released on 2003 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance by : D. V. Rao
Download or read book Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance written by D. V. Rao and published by . This book was released on 2003 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance by : D. V. Rao
Download or read book Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance written by D. V. Rao and published by . This book was released on 2003-03-01 with total page 298 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Debris Impact on Emergency Coolant Recirculation by :
Download or read book Debris Impact on Emergency Coolant Recirculation written by and published by . This book was released on 2004 with total page 418 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pressurized Water Reactors by : Yurugi Kanzaki
Download or read book Pressurized Water Reactors written by Yurugi Kanzaki and published by Elsevier. This book was released on 2024-07-26 with total page 507 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned. The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own. Contains contributions from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes analysis codes, such as RELAP5, for the design and safety improvement of pressurized water reactors (PWRs) Presents history, examples, and case studies from Japan and other key regions, such as the United States and Europe
Download or read book GSI-191 written by M. L. Marshall and published by . This book was released on 2002 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Selected Bibliography on Emergency Core Cooling Systems (ECCS) for Light-water Cooled Power Reactors (LWRs) by : William B. Cottrell
Download or read book A Selected Bibliography on Emergency Core Cooling Systems (ECCS) for Light-water Cooled Power Reactors (LWRs) written by William B. Cottrell and published by . This book was released on 1974 with total page 194 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evaluation of Incidents of Primary Coolant Release from Operating Boiling Water Reactors by : United States. Atomic Energy Commission
Download or read book Evaluation of Incidents of Primary Coolant Release from Operating Boiling Water Reactors written by United States. Atomic Energy Commission and published by . This book was released on 1972 with total page 133 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Consequence Evaluation of In-vessel Fuel Coolant Interactions in the European Pressurized Water Reactor by :
Download or read book Consequence Evaluation of In-vessel Fuel Coolant Interactions in the European Pressurized Water Reactor written by and published by . This book was released on 1999 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Generic Aging Management Programs for License Renewal of BWR Reactor Coolant Systems Components by :
Download or read book Generic Aging Management Programs for License Renewal of BWR Reactor Coolant Systems Components written by and published by . This book was released on 2002 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The paper reviews the existing generic aging management programs (AMPs) for the reactor coolant system (RCS) components in boiling water reactors (BWRs), including the reactor pressure vessel and internals, the reactor recirculation system, and the connected piping. These programs have been evaluated in the U.S. Nuclear Regulatory Commission (NRC) report, Generic Aging Lessons Learned (GALL), NUREG-1801, for their use in the license renewal process to manage several aging effects, including loss of material, crack initiation and growth, loss of fracture toughness, loss of preload, wall thinning, and cumulative fatigue damage. The program evaluation includes a review of ten attributes (scope of program, preventive actions, parameters monitored/inspected, detection of aging effects, monitoring and trending, acceptance criteria, corrective actions, confirmative process, administrative control, and operating experience) for their effectiveness in managing a specific aging effect in a given component(s). The generic programs are based on the ASME Section XI inservice inspection requirements; industry guidelines for inspection and evaluation of aging effects in BWR reactor vessel, internals, and recirculation piping; monitoring and control of BWR water chemistry; and operating experience as reported in the USNRC generic communications and industry reports. The review concludes that all generic AMPs are acceptable for managing aging effects in BWR RCS components during an extended period of operation and do not need further evaluation. However, the plant-specific programs for managing aging in certain RCS components during an extended period of operation do require further evaluation. For some plant-specific AMPs, the GALL report recommends an aging management activity to verify their effectiveness. An example of such an activity is a one-time inspection of Class 1 small-bore piping to ensure that service-induced weld cracking is not occurring in the piping. Several of the AMPs, which do not require further evaluation, do need enhancements to allow for an extended period of reactor operation. The paper concludes that the GALL report systematically evaluates the generic AMPs for their effectiveness during an extended period of operation and provides a technical basis for their acceptance. The use of the GALL report should facilitate both preparation of a license renewal application and timely and uniform review by the NRC staff.
Book Synopsis On Fuel Coolant Interactions and Debris Coolability in Light Water Reactors by :
Download or read book On Fuel Coolant Interactions and Debris Coolability in Light Water Reactors written by and published by . This book was released on 2015 with total page 85 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Engineering Test Program to Investigate a Loss of Coolant Accident by : T. R. Wilson
Download or read book An Engineering Test Program to Investigate a Loss of Coolant Accident written by T. R. Wilson and published by . This book was released on 1964 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Experimental Investigation on the Effects of Coolant Concentration on Sub-Cooled Boiling and Crud Deposition on Reactor Cladding at Prototypical PWR Operating Conditions by : J. Schultis (Kenneth)
Download or read book Experimental Investigation on the Effects of Coolant Concentration on Sub-Cooled Boiling and Crud Deposition on Reactor Cladding at Prototypical PWR Operating Conditions written by J. Schultis (Kenneth) and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Increasing demand for energy necessitates nuclear power units to increase power limits. This implies significant changes in the design of the core of the nuclear power units, therefore providing better performance and safety in operations. A major hindrance to the increase of nuclear reactor performance especially in Pressurized Deionized water Reactors (PWR) is Axial Offset Anomaly (AOA)--the unexpected change in the core axial power distribution during operation from the predicted distribution. This problem is thought to be occur because of precipitation and deposition of lithiated compounds like boric acid (H{sub 2}BO{sub 3}) and lithium metaborate (LiBO{sub 2}) on the fuel rod cladding. Deposited boron absorbs neutrons thereby affecting the total power distribution inside the reactor. AOA is thought to occur when there is sufficient build-up of crud deposits on the cladding during subcooled nucleate boiling. Predicting AOA is difficult as there is very little information regarding the heat and mass transfer during subcooled nucleate boiling. An experimental investigation was conducted to study the heat transfer characteristics during subcooled nucleate boiling at prototypical PWR conditions. Pool boiling tests were conducted with varying concentrations of lithium metaborate (LiBO{sub 2}) and boric acid (H{sub 2}BO{sub 3}) solutions in deionized water. The experimental data collected includes the effect of coolant concentration, subcooling, system pressure and heat flux on pool the boiling heat transfer coefficient. The analysis of particulate deposits formed on the fuel cladding surface during subcooled nucleate boiling was also performed. The results indicate that the pool boiling heat transfer coefficient degrades in the presence of boric acid and lithium metaborate compared to pure deionized water due to lesser nucleation. The pool boiling heat transfer coefficients decreased by about 24% for 5000 ppm concentrated boric acid solution and by 27% for 5000 ppm lithium metaborate solution respectively at the saturation temperature for 1000 psi (68.9 bar) coolant pressure. Boiling tests also revealed the formation of fine deposits of boron and lithium on the cladding surface which degraded the heat transfer rates. The boron and lithium metaborate precipitates after a 5 day test at 5000 ppm concentration and 1000 psi (68.9 bar) operating pressure reduced the heat transfer rate 21% and 30%, respectively for the two solutions.
Book Synopsis Generic Assessment of Delayed Reactor Coolant Pump Trip During Small Break Loss-of-coolant Accidents in Pressurized Water Reactors by : Brian Sheron
Download or read book Generic Assessment of Delayed Reactor Coolant Pump Trip During Small Break Loss-of-coolant Accidents in Pressurized Water Reactors written by Brian Sheron and published by . This book was released on 1979 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Consequence Evaluation of In-vessel Fuel Coolant Interactionsin the European Pressurized Water Reactor by : U. (and others). Imke
Download or read book Consequence Evaluation of In-vessel Fuel Coolant Interactionsin the European Pressurized Water Reactor written by U. (and others). Imke and published by . This book was released on 1999 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:
