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

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Subjects:

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

Edition Notes

Book details

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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Risk assessment of severe accident-induced steam generator tube rupture (SuDoc Y 3.N /) on *FREE* shipping on qualifying cturer: Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S.

Nuclear Regulatory Commission. Get this from a library. Risk assessment of severe accident-induced steam generator tube rupture. [U.S. Nuclear Regulatory Commission. SGTR Severe Risk assessment of severe accident-induced steam generator tube rupture book Working Group.; U.S.

Nuclear Regulatory Commission. Division of Systems Safety and Analysis.;]. 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 | OnMohamad 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. A steam generator tube rupture (SGTR) accident analysis for SMART was performed using the TASS/SMR-S code.

SMART with a rated thermal power of MWt has been developed at the Korea Atomic Energy Research Institute. operational aspects. However, steam generator tube leakage incidents have proven that such occurrence cannot be completely ruled out.

If a steam generator tube ruptures during a severe accident, radionuclides may leak from primary circuit to the secondary side and bypass the containment.

@article{osti_, title = {Steam generator tube failures}, author = {MacDonald, P E and Shah, V N and Ward, L W and Ellison, P G}, abstractNote = {A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented.

The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium. A Steam Generator Tube Rupture (SGTR) in a Pressurized Water Reactor (PWR) can lead to an atmospheric release bypassing the containment via the secondary system and exiting though the Pressurized Operating Relief Valves of the affected Steam Generator.

That is why SGTR historically have been treated in a special way in the different Deterministic. Pesetti, Alessio, Tarantino, Mariano, and Forgione, Nicola. "Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code." Proceedings of the 26th International Conference on Nuclear Engineering.

Risk assessment of severe accident-induced steam generator tube rupture, U.S. Nuclear Regulatory Commission, NUREG, 6 Boyd C F, Hardesty K.

Analysis of 1/7 scale steam generator inlet plenum mixing during a PWR severe accident, U.S. Nuclear Regulatory Commission, NUREG, 7 Boyd C F, Helton D M. Hardesty K. Analysis of full. This report summarizes severe-accident-induced consequential steam generator (SG) tube rupture (C-SGTR) analyses recently performed by the U.S.

Nuclear Regulatory Commission's (NRC's) Office of Nuclear Regulatory Research. C-SGTRs are potentially risk-significant events because thermally induced SG tube failures caused by hot gases from a.

[3] U.S. NRC, Risk assessment of severe accident-induced steam generator tube rupture, U.S. Nuclear Regulatory Commission Report, NUREG, (). DOI: / [4] Y. Liao, S. Guentay, Potential steam generator tube rupture in the presence of severe accident thermal challenge and tube flaws due to foreign object wear, Nuclear.

[1] INEEL/EXT, “SCDAP/RELAP5 Evaluation Of The Potential For Steam Generator Tube Ruptures As A Result Of Severe Accidents In Operating Pressurized Water Reactors”, Revision 1, INEEL. Also researches on the containment bypass scenarios such as severe accident induced steam generator tube rupture and interfacing system LOCA (Loss of Coolant Accident) are begin carried out, where the accident progression during the bypass events and effect of mitigation actions by the operator are simulated by severe accident computer codes.

In MarchPalo Verde Nuclear Generating Station`s Unit 2 sustained a tube rupture within steam generator A search for the root cause of failure identified intergranular stress corrosion cracking (IGSCC) in the hot leg upper bundle. Subsequent eddy current inspections and tube pull evaluations supported this conclusion.

approach will be comparable to that of the previous RES C-SGTR risk report and the earlier NUREG, “Risk Assessment of Severe Accident-Induced Steam Generator Tube Rupture,” study.

Consistent with our previous C-SGTR risk assessment work, the new simplified method will include consideration of both pressure-induced and. Abstract. Severe plant transients, following a steam generator tube rupture (SGTR), have a relatively high probability of occurrence and may entrain a certain risk.

Steam generator tube rupture (SGTR) accident is one of important accident that has high probability of resulting in severe accidents. As a bypass scenario, fission product can be directly released to the environment during the SGTR accident. Thus, the severe accident by SGTR should be carefully managed by severe accident management guidance (SAMG).

USNRC, Risk assessment of severe accident-induced steam generator tube rupture, NUREG () 5. USNRC, MELCOR Computer Code Manuals, vol. 3, NUREG/CR (). uncertainty on the risk measures quantified. In this paper, we demonstrate the CB-PSA with reference to a spontaneous Steam Generator Tube Rupture (SGTR) accident scenario in a Pressurized Water Reactor (PWR).

Results show that the updated risk measures are capable of reflecting the actual state of the SG in the tailored risk evaluation. Gu¨ntay, Salih, Dehbi, Abdel, Suckow, Detlef, and Birchley, Jon.

"The PSI Artist Project: Aerosol Retention and Accident Management Issues Following a Steam Generator Tube Rupture." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. Use of SCDAP/RELAP5 results in severe accident-induced tube rupture risk assessment Journal Article Donoghue, J.

; Lee, R. - Transactions of the American Nuclear Society This study was conducted to provide the basis for an estimate of the containment bypass risk presented by severe accident-induced steam generator tube rupture.

A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the.

This report summarizes severe accident-induced consequential steam generator tube rupture (C-SGTR) analyses recently Start Printed Page performed by the NRC's Office of Nuclear Regulatory Research.

The analyses described in this report include risk assessment, thermal-hydraulic analyses, and materials behavior analyses. Steam Generator Tube Rupture (SGTR) event leads to contamination of the secondary side due to leakage of the radioactive coolant from the Reactor Coolant System (RCS) through the broken Steam Generator (SG) tube(s).

The major concern for the SGTR event is the release of contaminated liquid through the secondary side relief valves to the atmosphere. IN USE: STEAM GENERATOR TUBE INTEGRITY ASSESSMENT ISSUE More than 50% of the PWR reactor coolant pressure bound - ary is comprised of the heat transfer tubes in the steam gen-erators.

Ineffective or inaccurate tube integrity assessments steam generator tube rupture, or a reduction in margin against design basis accidents. During an extreme situation of SBO transient, steam generator (SG) U-tube integrity could be threatened by thermally or pressure-induced creep rupture [11].

The SGTR accident induced by SBO releases more fission products to environment because many safety features such as auxiliary feed water (AFW) are inoperable.

Rupture of a steam generator tube can result in release of fission products to environment. Therefore, an accurate integrity assessment of the steam generator tubes with cracks is of great importance for maintaining safety of a nuclear power plant.

Improvement of steam generator tube failure propagation analysis code LEAP for evaluation of overheating rupture. Journal of Nuclear Science and Technology: Vol. 56, No. 2, pp. Capabilities are demonstrated by results of analysis of steam generator no. 1 in Slovenian nuclear power plant located in Krsˇko after the inspection and plugging campaign.

First, the number of cracked tubes and the crack length distribution were estimated using data obtained by the percent motorized pancake coil inspection. DRAFT DRAFT DRAFT DRAFT Methodology for Assessing Severe Accident-Induced Steam Generator Tube Rupture Prepared by: David R.

Bradley and Paul J. Amico Get this from a library! Risk assessment of severe accident- induced steam generator tube rupture.The control room operators assume that a steam generator tube rupture (SGTR) had occurred and estimate that the makeup flow (including safety injection) to be about gpm.

The increase in steam generator pressure caused the high-pressure safety relief valves to open briefly, but subsequently the increased steam generator pressure is.Before switching on the steam generator ensure the steam outlet valve is closed and the valves to the appliances are closed Switch on the steam generator and watch the pressure dial build to 30 psi.

At this pressure, or just above, the controller should be observed to regulate the pressure to 30 psi.

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