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Simulation Of A Loss Of Coolant Accident With Rupture In The Steam Generator Hot Collector
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Author :Standard Problem Exercise on the Simulation of Loss of Coolant Accidents Publisher : ISBN 13 : Total Pages :319 pages Book Rating :4.:/5 (172 download)
Book Synopsis Simulation of a loss of coolant accident with rupture in the steam generator hot collector by : Standard Problem Exercise on the Simulation of Loss of Coolant Accidents
Download or read book Simulation of a loss of coolant accident with rupture in the steam generator hot collector written by Standard Problem Exercise on the Simulation of Loss of Coolant Accidents and published by . This book was released on 1991 with total page 319 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Simulation of a Loss of Coolant Accident with Rupture in the Steam Generator Hot Collector by :
Download or read book Simulation of a Loss of Coolant Accident with Rupture in the Steam Generator Hot Collector written by and published by . This book was released on 1991 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Simulation of a Loss of Coolant Accident with Rupture in the Steam Generator Hot Collector by :
Download or read book Simulation of a Loss of Coolant Accident with Rupture in the Steam Generator Hot Collector written by and published by . This book was released on 1991 with total page 319 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-06 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Steam Generator Tube Rupture Effects on a LOCA. by :
Download or read book Steam Generator Tube Rupture Effects on a LOCA. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A problem currently experienced in commercial operating pressurized water reactors (PWR) in the United States is the degradation of steam generator tubes. Safety questions have arisen concerning the effect of these degraded tubes rupturing during a postulated loss-of-coolant accident (LOCA). To determine the effect of a small number of tube ruptures on the behavior of a large PWR during a postulated LOCA, a series of computer simulations was performed. The primary concern of the study was to determine whether a small number (10 or less of steam generator tubes rupturing at the beginning surface temperatures. Additional reflood analyses were performed to determine the system behavior when from 10 to 60 tubes rupture at the beginning of core reflood. The FLOOD4 code was selected as being the most applicable code for use in this study after an extensive analysis of the capabilities of existing codes to perform simulations of a LOCA with concurrent steam generator tube ruptures. The results of the study indicate that the rupturing of 10 or less steam generator tubes in any of the steam generators during a 200% cold leg break will not result in a significant increase in the peak cladding temperature. However, because of the vaporization of the steam generator secondary water in the primary side of the steam generator, a significant increase in the core pressure occurs which retards the reflooding process.
Book Synopsis Experiment Data Report for Semiscale Mod-1 Test S-28-4 (steam Generator Tube Rupture Test). by :
Download or read book Experiment Data Report for Semiscale Mod-1 Test S-28-4 (steam Generator Tube Rupture Test). written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recorded test data are presented for Test S-28-4 of the Semiscale Mod-1 steam generator tube rupture test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-28-4 was conducted from initial conditions of 15 646 kPa and 557 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. During the test, cooling water was injected into the cold leg of the intact and broken loops to simulate emergency core coolant injection in a PWR. Thirty steam generator tube ruptures were simulated by a controlled injection from a heated accumulator into the intact loop hot leg.
Book Synopsis Experiment Data Report for Semiscale Mod-1 Test S-28-1 (steam Generator Tube Rupture Test Series). by :
Download or read book Experiment Data Report for Semiscale Mod-1 Test S-28-1 (steam Generator Tube Rupture Test Series). written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recorded test data are presented for Test S-28-1 of the Semiscale Mod-1 steam generator tube rupture test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-28-1 was conducted from initial conditions of 15 767 kPa and 557 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. During the test, cooling water was injected into the cold leg of the intact and broken loops to simulate emergency core coolant injection in a PWR. Sixty steam generator tube ruptures were simulated by a controlled injection from a heated accumulator into the intact loop hot leg.
Book Synopsis Validation of Systems Transients Analysis Codes by : Richard R. Schultz
Download or read book Validation of Systems Transients Analysis Codes written by Richard R. Schultz and published by . This book was released on 1995 with total page 208 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modeling of Once-through Steam Generator Thermal-hydraulics During a Loss of Coolant Accident by : Brij Kumar Kamboj
Download or read book Modeling of Once-through Steam Generator Thermal-hydraulics During a Loss of Coolant Accident written by Brij Kumar Kamboj and published by . This book was released on 1993 with total page 626 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Loads on Steam Generator Tubes During Simulated Loss-of-coolant Accident Conditions by :
Download or read book Loads on Steam Generator Tubes During Simulated Loss-of-coolant Accident Conditions written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Transactions of the American Nuclear Society by :
Download or read book Transactions of the American Nuclear Society written by and published by . This book was released on 1991 with total page 500 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Simulation of Steam Generator Tube Rupture Accident by Safety Analysis Code RELAP5/MOD1 by : Akio Gofuku
Download or read book A Simulation of Steam Generator Tube Rupture Accident by Safety Analysis Code RELAP5/MOD1 written by Akio Gofuku and published by . This book was released on 1989 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Simulators International XII by : Maurice Ades
Download or read book Simulators International XII written by Maurice Ades and published by Society for Computer Simulation International. This book was released on 1995 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Human Reliability Assessment Theory and Practice by : Anthony J. Spurgin
Download or read book Human Reliability Assessment Theory and Practice written by Anthony J. Spurgin and published by CRC Press. This book was released on 2009-10-08 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt: A continually evolving discipline, human reliability assessment (HRA) has elements of controversy from the definition of terms to the application of appropriate methods for the representation of human failure probability. The idea that human error is a random event is falling out of favor and the concept that humans can be set up to fail or succeed
Download or read book Nuclear Technology written by and published by . This book was released on 1991 with total page 416 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reviewing the Safety of Existing Nuclear Power Plants by : International Atomic Energy Agency
Download or read book Reviewing the Safety of Existing Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 1997 with total page 688 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of a symposium organized in co-operation with OECD/NEA, Vienna, 8-11 October 1996. The symposium was a follow-up to the 1991 International Conference on The Safety of Nuclear Power: Strategy for the Future and will be remembered as the initiating force behind the Convention on Nuclear Safety, which entered into force on 24 October 1996. The goal was to review the progress made in implementing the recommendations of the 1991 Conference relating to the safety of existing nuclear power plants, and to make available to all those involved in maintaining the safety of nuclear power plants information on effective methods, practices and criteria for safety review and operating experience feedback systems.
Book Synopsis Evaluation of Fire Hazard Analyses for Nuclear Power Plants by : International Atomic Energy Agency
Download or read book Evaluation of Fire Hazard Analyses for Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 1995 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides a detailed list of the issues, and some of the limitations, to be considered when evaluating the adequacy and effectiveness of the fire hazard analysis of a nuclear power plant. It further gives a broad description of the methodology to be used by operators in preparing a fire hazard analysis for their own plant.
