A Retran Model For A Hypothetical Steam Line Break Occurring At Low Power Operation Of The Trojan Nuclear Plant
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A Retran Model For A Hypothetical Steam Line Break Occurring At Low Power Operation Of The Trojan Nuclear Plant
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Author : Peter John Jensen
language : en
Publisher:
Release Date : 1983
A Retran Model For A Hypothetical Steam Line Break Occurring At Low Power Operation Of The Trojan Nuclear Plant written by Peter John Jensen and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1983 with Steam-pipes categories.
The goal of this study is the modeling of a postulated break of the steam line at the containment penetration of the Trojan Nuclear Plant which is owned and operated by Portland General Electric. To perform this modeling, the RETRAN computer code package was utilized. RETRAN is designed to provide a best-estimate thermal hydraulic analysis of complex fluid flow systems such as those associated with light water reactors, solving both steady state and time dependent problems. A one loop RETRAN model of the Trojan Nuclear Plant including both a primary system and one steam generator had been developed previously at Oregon State University and was used as a starting point. The first step of this study was the refinement of the model into a two loop model. Since Trojan has four actual loops, one modeling loop represents three actual loops and the other modeling loop represents one actual loop. This allows the simulation of a transient introduced in one loop only, in contrast to the one loop model which requires introduction of the transient in all four loops simultaneously The second step in this study was to establish a steady state solution at four percent power consistent with the 100 percent power solution. Since the steam generator outlet pressure increases as power decreases, steam line break flow rates will be higher at low power, yielding a more conservative result (higher mass and energy release rates). Although hot standby (zero power) implies the highest outlet pressure, four percent power was used for modeling convenience: fewer alterations to the existing model were required with no loss of accuracy. The final step of the study consisted of including the steam lines in the RETRAN model and the simulation of a steam line break at a weld at the penetration of the primary containment. This weld was of particular interest because its location makes inspection and maintenance difficult. The transient was modeled for the relatively short time span of two seconds since maximum flow and energy release rates occurring during this interval were of primary interest.
Masters Theses In The Pure And Applied Sciences
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Author : Wade H. Shafer
language : en
Publisher: Springer Science & Business Media
Release Date : 2012-12-06
Masters Theses In The Pure And Applied Sciences written by Wade H. Shafer and has been published by Springer Science & Business Media this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012-12-06 with Science categories.
Masters Theses in the Pure and Applied Sciences was first conceived, published, and disseminated by the Center for Information and Numerical Data Analysis and Synthesis (CINDAS) * at Purdue University in 1 957, starting its coverage of theses with the academic year 1955. Beginning with Volume 13, the printing and dissemination phases of the activity were transferred to University Microfilms/Xerox of Ann Arbor, Michigan, with the thought that such an arrangement would be more beneficial to the academic and general scientific and technical community. After five years of this joint undertaking we had concluded that it was in the interest of all con cerned if the printing and distribution of the volumes were handled by an interna tional publishing house to assure improved service and broader dissemination. Hence, starting with Volume 18, Masters Theses in the Pure and Applied Sciences has been disseminated on a worldwide basis by Plenum Publishing Cor poration of New York, and in the same year the coverage was broadened to include Canadian universities. All back issues can also be ordered from Plenum. We have reported in Volume 29 (thesis year 1984) a total of 12,637 theses titles from 23 Canadian and 202 United States universities. We are sure that this broader base for these titles reported will greatly enhance the value of this important annual reference work. While Volume 29 reports theses submitted in 1984, on occasion, certain univer sities do report theses submitted in previous years but not reported at the time.
Analysis Of Steam Line Break Transient With Relap5
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Author :
language : en
Publisher:
Release Date : 1983
Analysis Of Steam Line Break Transient With Relap5 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1983 with categories.
Section 15.1.5 of the Standard Review Plant outlines the areas of review and the acceptance criteria for the analysis of steam system piping failures inside and outside of containment. Combustion Engineering (C-E) submitted analysis of the limiting steam line break (SLB) transient for the C-E 3800 MW nuclear steam supply system as Appendix 15C to the CESSAR FSAR. Conservative initial conditions and analysis assumptions were utilized in the transient calculation which was performed with the CESEC-III computer program. Argonne National Laboratory (ANL), under contract to the Nuclear Regulatory Commission, performed audit calculations of SLB transients presented in the CESSAR FSAR, with RELAP5/MOD1.5 (Cycle 26) and compared them with the CE results. The transient presented here is a large steam line break during full power operation with a concurrent loss of offsite power. The objective of this study was to examine the impact of mixing of cold primary fluid returning to the core from the affected steam generator with the hot fluid returning from the intact side, and its effect upon the potential return to power due to moderator feedback.
Main Steam Line Break Accident Analysis For Maanshan Nuclear Power Plant Using Relap5 Mod1 Code
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Author : Kuo-Shing Liang
language : en
Publisher:
Release Date : 1986
Main Steam Line Break Accident Analysis For Maanshan Nuclear Power Plant Using Relap5 Mod1 Code written by Kuo-Shing Liang and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1986 with categories.
Evaluation Of A Main Steam Line Break With Induced Multiple Tube Ruptures
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Author :
language : en
Publisher:
Release Date : 1995
Evaluation Of A Main Steam Line Break With Induced Multiple Tube Ruptures written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1995 with categories.
This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2.
Main Steam Line Break Accident Analysis For Maanshan Units 1 2 Using Retran 02 Mod2 Code
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Author : Jan-Ru Tang
language : en
Publisher:
Release Date : 1986
Main Steam Line Break Accident Analysis For Maanshan Units 1 2 Using Retran 02 Mod2 Code written by Jan-Ru Tang and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1986 with categories.
Wolf Creek Steam Line Break Analysis Comparison Of Retran 02 Analysis With Updates Safety Analysis Report Project 2941
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Author : Wolf Creek Nuclear Operating Corporation
language : en
Publisher:
Release Date : 1990
Wolf Creek Steam Line Break Analysis Comparison Of Retran 02 Analysis With Updates Safety Analysis Report Project 2941 written by Wolf Creek Nuclear Operating Corporation and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1990 with categories.
Flash Predictions Of The Mb 2 Steam Line Break Tests
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Author :
language : en
Publisher:
Release Date : 1992
Flash Predictions Of The Mb 2 Steam Line Break Tests written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1992 with categories.
If a main steam line from a pressurized water reactor (PWR) steam generator were to rupture, the effect would be a depressurization of the secondary side and a consequential overcooling transient on the primary side. Analyses must accurately predict the effects of the rapid cooldown of the reactor vessel coolant on positive nuclear-kinetic reactivity feedback to the core plus thermal shock to the reactor vessel and other primary system components. Many early studies of the steam line break (SLB) transient made extremely conservative assumptions to maximize the primary to secondary heat transfer which in turn maximized the reactor vessel cooldown rate. Among the more significant of these assumptions was that flow from the break was pure steam and that the tube bundle remained covered until the secondary mass inventory was significantly reduced. The Model F commercial PWR steam generator testing performed in the Model Boiler No. 2 (MB-2) facility located at the Westinghouse Engineering Test Facility in Tampa, Florida provided data to better qualify the actual variation in these key parameters. A conclusion of this analysis is that the MB-2 steam line break data base is accurate and of sufficient detail to provide a valuable basis for making comparisons relative to code predictions. Results obtained using the FLASH transient safety analysis code were found to be in excellent agreement with the data.
Nuclear Energy Today
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Author : OECD Nuclear Energy Agency
language : en
Publisher: OECD
Release Date : 2003
Nuclear Energy Today written by OECD Nuclear Energy Agency and has been published by OECD this book supported file pdf, txt, epub, kindle and other format this book has been release on 2003 with Business & Economics categories.
As energy demand increases in line with the expansion of the world's leading economies and the growth of developing economies, a key challenge remains of how to provide the energy levels required while protecting our environment and conserving natural resources. Nuclear energy is a complex and controversial technology but also has the potential to provide considerable benefits. This publication explores a range of issues involved in the use of nuclear energy, including safety aspects, whether its use is economically competitive, its role in meeting greenhouse gas reduction targets, how to manage the radioactive waste it generates, whether its use increase the risk of proliferation of nuclear weapons, security of resources, and its potential role in the future.
The Technological And Economic Future Of Nuclear Power
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Author : Reinhard Haas
language : en
Publisher: Springer
Release Date : 2019-01-01
The Technological And Economic Future Of Nuclear Power written by Reinhard Haas and has been published by Springer this book supported file pdf, txt, epub, kindle and other format this book has been release on 2019-01-01 with Agriculture (General) categories.
This open access book discusses the eroding economics of nuclear power for electricity generation as well as technical, legal, and political acceptance issues. The use of nuclear power for electricity generation is still a heavily disputed issue. Aside from technical risks, safety issues, and the unsolved problem of nuclear waste disposal, the economic performance is currently a major barrier. In recent years, the costs have skyrocketed especially in the European countries and North America. At the same time, the costs of alternatives such as photovoltaics and wind power have significantly decreased. Contents History and Current Status of the World Nuclear Industry The Dramatic Decrease of the Economics of Nuclear Power Nuclear Policy in the EU The Legacy of Csernobyl and Fukushima Nuclear Waste and Decommissioning of Nuclear Power Plants Alternatives: Heading Towards Sustainable Electricity Systems Target Groups Researchers and students in the fields of political, economic and technical sciences Energy (policy) experts, nuclear energy experts and practitioners, economists, engineers, consultants, civil society organizations The Editors Prof. Dr. Reinhard Haas is University Professor of energy economics at the Institute of Energy Systems and Electric Drives at Technische Universität Wien, Austria. PD Dr. Lutz Mez is Associate Professor at the Department for Political and Social Sciences of Freie Universität Berlin, Germany. PD Dr. Amela Ajanovic is a senior researcher and lecturer at the Institute of Energy Systems and Electrical Drives at Technische Universität Wien, Austria.--
