Analysis Of Steam Generator Tube Rupture As A Severe Accident Using Melcor 184 PDF Download
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Author | : Hongrun Yang |
Publisher | : |
Total Pages | : 110 |
Release | : 1999 |
Genre | : Fusion reactors |
ISBN | : |
Download Analysis of Steam Generator Tube Rupture as a Severe Accident Using MELCOR 1.8.4 Book in PDF, ePub and Kindle
Author | : |
Publisher | : |
Total Pages | : 218 |
Release | : 1998 |
Genre | : |
ISBN | : |
Download Risk Assessment of Severe Accident-induced Steam Generator Tube Rupture Book in PDF, ePub and Kindle
This report describes the basis, results, and related risk implications of an analysis performed by an ad hoc working group of the U.S. Nuclear Regulatory Commission (NRC) to assess the containment bypass potential attributable to steam generator tube rupture (SGTR) induced by severe accident conditions. The SGTR Severe Accident Working Group, comprised of staff members from the NRC's Offices of Nuclear Reactor Regulation (NRR) and Nuclear Regulatory Research (RES), undertook the analysis beginning in December 1995 to support a proposed steam generator integrity rule. The work drew upon previous risk and thermal-hydraulic analyses of core damage sequences, with a focus on the Surry plant as a representative example. This analysis yielded new results, however, derived by predicting thermal-hydraulic conditions of selected severe accident scenarios using the SCDAP/RELAP5 computer code, flawed tube failure modeling, and tube failure probability estimates. These results, in terms of containment bypass probability, form the basis for the findings presented in this report. The representative calculation using Surry plant data indicates that some existing plants could be vulnerable to containment bypass resulting from tube failure during severe accidents. To specifically identify the population of plants that may pose a significant bypass risk would require more definitive analysis considering uncertainties in some assumptions and plant- and design-specific variables. 46 refs., 62 figs., 37 tabs.
Author | : Chʻun-fa Chuang |
Publisher | : |
Total Pages | : 217 |
Release | : 1983 |
Genre | : |
ISBN | : |
Download Consequence Analysis for a Steam Generator Tube Rupture Accident Book in PDF, ePub and Kindle
Author | : United States Government Printing Office |
Publisher | : |
Total Pages | : 224 |
Release | : 1998-03-01 |
Genre | : |
ISBN | : 9780160627293 |
Download Risk Assessment of Severe Accident Induced Steam Generator Tube Rupture Book in PDF, ePub and Kindle
Author | : U.S. Nuclear Regulatory Commission |
Publisher | : |
Total Pages | : 28 |
Release | : 1997 |
Genre | : Pressurized water reactors |
ISBN | : |
Download Risk Assessment of Severe Accident-induced Steam Generator Tube Rupture Book in PDF, ePub and Kindle
Author | : L. B. Marsh |
Publisher | : |
Total Pages | : 132 |
Release | : 1980 |
Genre | : Pressurized water reactors |
ISBN | : |
Download Evaluation of Steam Generator Tube Rupture Events Book in PDF, ePub and Kindle
Author | : B. A. Kashiwa |
Publisher | : |
Total Pages | : 80 |
Release | : 1985 |
Genre | : Fluid dynamics |
ISBN | : |
Download Analytic Studies Pertaining to Steam Generator Tube Rupture Accidents Book in PDF, ePub and Kindle
Author | : V. Benčik |
Publisher | : |
Total Pages | : 0 |
Release | : 2014 |
Genre | : Nuclear power plants |
ISBN | : |
Download RELAP5/MOD3.3 Analysis of Steam Generator Tube Rupture (SGTR) Accident for NPP Krško Book in PDF, ePub and Kindle
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1986 |
Genre | : |
ISBN | : |
Download Analysis of Steam-generator Tube-rupture Events Combined with Auxiliary-feedwater Control-system Failure for Three Mile Island-Unit 1 and Zion-Unit 1 Pressurized Water Reactors Book in PDF, ePub and Kindle
A steam-generator tube-rupture (SGTR) event combined with loss of all offsite alternating-current power and failure of the auxiliary-feedwater (AFW) control system has been investigated for the Three Mile Island-Unit 1 (TMI-1) and Zion-Unit 1 (Zion-1) pressurized water reactors. The Transient Reactor Analysis Code was used to simulate the accident sequence for each plant. The objectives of the study were to predict the plant transient response with respect to tube-rupture flow termination, extent of steam generator overfill, and thermal-hydraulic conditions in the steam lines. Two transient cases were calculated: (1) a TMI-1 SGTR and runaway-AFW transient, and (2) a Zion-1 SGTR and runaway-AFW transient. Operator actions terminated the tube-rupture flow by 1342 s (22.4 min) and 1440 s (24.0 min) for TMI-1 and Zion-1, respectively, but AFW injection was continued. The damaged steam generator (DSG) overfilled by 1273 s (21.2 min) for the TMI-1 calculation and by 1604 s (26.7 min) for the Zion-1 calculation. The DSG steam lines were completely filled by 1500 s (25 min) and 2000 s (33.3 min) for TMI-1 and Zion-1, respectively. The maximum subcooling in the steam lines was approx. 63 K (approx. 113°F) for TMI-1 and approx. 44 K (approx. 80°F) for Zion-1.
Author | : V. Benčik |
Publisher | : |
Total Pages | : 55 |
Release | : 2014 |
Genre | : Nuclear power plants |
ISBN | : |
Download RELAP5/MOD3.3 Analysis of Steam Generator Tube Rupture (SGTR) Accident for NPP Krško Book in PDF, ePub and Kindle