Risk assessment of severe accident-induced steam generator tube rupture
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Risk assessment of severe accident-induced steam generator tube rupture

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Published by Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC .
Written in English

Subjects:

  • Nuclear power plants -- Piping -- Reliability,
  • Nuclear reactors -- Containment,
  • Nuclear power plants -- Risk assessment

Book details:

Edition Notes

Other titlesRisk assessment of severe accident induced steam generator tube rupture
StatementSGTR Severe Accident Working Group
ContributionsU.S. Nuclear Regulatory Commission. SGTR Severe Accident Working Group, U.S. Nuclear Regulatory Commission. Division of Systems Safety and Analysis
The Physical Object
FormatMicroform
Pagination1 v. (various pagings)
ID Numbers
Open LibraryOL15256211M

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Severe Accident Initiated Steam Generator Tube Ruptures Leading to Containment Bypass – Integrated Risk Assessment February Letter Report February Prepared by: J.L. LaChance, D. Kunsman, and J. Forester Sandia National Laboratories Albuquerque, NM P.J. Amico, D.R. Bradley, and A. Kolaczkowski. accidents resulting in severe accident-induced steam generator tube rupture (SAI-SGTR). The methodology has been developed based on the assumption that such an assessment would be a risk-informed application under Regulatory Guide (USNRC, b). This assumption implies specific requirements for both the. Types of steam tube rupture accident. Steam generators (SGs) are part of the Nuclear Steam Supply System (NSSS) at pressurized water reactor s and are thereto transfer heat from the primary system to the secondary system. A steam generator consists of many tubes carrying primary coolant at high pressure. The. The severe accident induced by station blackout (SBO) could lead to a long-term and high pressure sequence with inappropriate mitigation and the risk of creep rupture of steam generator (SG) tubes.

The objective of this paper is to present and analyze the results of simulated tube rupture accident in VVER Nuclear Reactor in PCTRAN. In simulating the accident, % of one full tube rupture has been considered. The simulation result shows. This study develops a methodology to assess the probability for the degraded PWR steam generator to rupture first in the reactor coolant pressure boundary, under severe accident conditions with countercurrent natural circulating high temperature gas in the hot leg and SG tubes. The first step performs thermal-hydraulic analysis to predict the creep rupture parameter of the tubes in severe.   Though previous steam generator tube rupture (SGTR) events, such as eleven events in the United States during – (Longmire, ), did not lead to a core damage due to actuations of robust plant safety systems and proper and timely operator actions, there is a risk significance on the radiological consequences for hypothetical SGTR. Main steam line break and steam generator tube rupture (SGTR) are both included as design basis accidents in Chapter 15 of most FSARs and the SRP and they are addressed as accident initiators in most plant-specific PRAs. However, these accident initiators are generally assumed to occur independently unless there is severe core damage. Moreover, a.

PDF | On , Mohamad Ali Azarm and others published SIMPLIFIED METHOD FOR ASSESSING THE RISK ASSOCIATED WITH CONSEQUENTIAL STEAM GENERATOR TUBE RUPTURE EVENTS | Find, read and cite all.   The steam generator tube rupture (SGTR) scenarios project was carried out in the EU 5th framework programme in the field of nuclear safety during years – The first objective of the project was to generate a comprehensive database on fission product retention in a steam generator.   Analysis of hypothetical severe accidents with current simplified flooding models shows that these models represent the largest uncertainty in steam generator tube creep rupture. Risk assessment of severe accident-induced steam generator tube rupture Technical Report 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.