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Wednesday, July 29, 2020 | History

2 edition of Radioactivity transport following steam generator tube rupture found in the catalog.

Radioactivity transport following steam generator tube rupture

J. Hopenfeld

Radioactivity transport following steam generator tube rupture

by J. Hopenfeld

  • 219 Want to read
  • 6 Currently reading

Published by Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, D.C .
Written in English

    Subjects:
  • Steam-boilers,
  • Radioactive pollution -- Measurement

  • Edition Notes

    ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Experimental Programs Branch
    The Physical Object
    Paginationvii, 37 p. :
    Number of Pages37
    ID Numbers
    Open LibraryOL14948157M

      WASHINGTON -- The rupture of a steam generator tube that triggered Monday's accident at the Ginna nuclear plant in Ontario, N.Y., is part . (). 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.

    Abstract. 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. @article{osti_, title = {Assessment of dose during an SGTR. [Steam Generator Tube Rupture (SGTR)]}, author = {Adams, J.P.}, abstractNote = {The Nuclear Regulatory Commission requires utilities to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant.

    E-0, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal; E-0, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, and ECA, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, when secondary radiation . 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.


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Radioactivity transport following steam generator tube rupture by J. Hopenfeld Download PDF EPUB FB2

Get this from a library. Radioactivity transport following steam generator tube rupture. [J Hopenfeld; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of. through tube walls without mixing and produces steam, which is then used to run turbines to produce electricity.

Steam generator tube is one of the many barriers between radioactive coolant and the environment. A damage to this barrier (i.e. rupturing of SG tubes) may allow release of radioactivity to the environmentdirectly, posing a serious.

Information Notice No. Steam Generator Tube Ruptures at Two PWR Facilities IN Novem MEMORANDUM FOR: B. Grier, Director, Region I J.

O'Reilly, Director, Region II J. Keppler, Director, Region III K. Seyfrit, Director, Region IV R. Engelken, Director, Region V FROM: Norman C. Moseley, Director, Division of Reactor Operations Inspection. A steam-generator-tube rupture (SGTR) in a pressurized-water reactor is a design-basis accident with which plants have been designed to cope.

Its specific significance is in its potential to bypass the containment thereby providing a pathway for radioactivity release to the : T. Lind, S. Campbell, L.E. Herranz, M. Kissane, JinHo Song. 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 by:   Even if a steam generator tube rupture occurs in SMART, the actuation of the passive residual heat removal system will help to confine the radioactivity material in the secondary system because the design pressure is MPa which is much higher than the design pressure of secondary side of commercial nuclear power plants.

CCNR Submission to CNSC: Transport of Radioactive Steam Generators 5 In a press release on used steam generators by the US Dept of Energy, describing a report entitled Shield design guide developed for construction of old steam generator storage facilities, we read: "In order to properly store decommissioned steam generators.

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. releases during a Steam Generator Tube Rupture (SGTR) event.

Discuss the primary-side and secondary-2 side indications of an SGTR in the control room. Discuss how the affected SG may be identified either prior to or following the reactor/turbine trip. 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. @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. While SGTR (Steam Generator Tube Rupture) accident occur, water in secondary side will inject to LBE in primary coolant, and flow with LBE.

The code of FLUENT will be used, steam is looked as particle, and standard k-ε model is used to predict turbulence variation of continuous phase in core. The DPM (Discrete Phase Model) will be used to.

A steam generator's heat-exchange tubes have an important safety role, because they separate radioactive and non-radioactive fluid systems. (The primary coolant becomes briefly radioactive from its exposure to the core, and also has trace amounts of longer-lived radioactive isotopes dissolved in it, such as dissolved atoms of iron from pipes.).

Steam generator tube performance criteria are established to ensure safe operation and to maintain the safety margins implied in the design and licensing basis for the nuclear pressure boundary for nuclear power plants. Requirements may vary slightly from jurisdiction to jurisdiction, but there are essentially three goals that are common among performance criteria.

For the purpose of simulating a rupture, an imaginary valve () was modeled between the tube side and the shell side of a steam generator. The secondary side feed-water system consists of main feed-water system (FWS) and emergency feed-water system (EFWS) modeled by time dependent volume andrespectively.

In tube rupture cases, the water is transferred through the steam generator blowdown system to a Liquid Waste Processing system, which includes storage tanks, ion exchangers, and radiation monitors.

Any releases via the waste processing system must meet the requirements of Title 10 of the Code of Federal Regulations, Part Within the framework of design and safety studies the impact of a steam generator tube rupture accident has been investigated.

In this postulated event high-pressured liquid water blasts into the lead pool which could trigger various transients. As a major concern steam could be dragged into the core featuring a positive void worth.

The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on Ma 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.

In WP1 the important accident scenarios for steam generator tube rupture were determined from existing PSA level 2 analysis, and by performing additional analyses with system level codes.

From these results the boundary conditions for the experimental studies were defined. In WP2, scaled-down models of a western PWR type steam generator and a.

Steam Generator Tube Rupture (SGTR) Multiple Steam Generator Tubes Rupture (MSGTR) Release of radioactive material outside the containment.

The safety margin is measured by: A. Large NPPs: • The following best -estimate assumptions are considered. steam generator tube failure accident, using the two iodine concentrations in item (6) above. A breathing rate of x m3/sec is used in the calculation of thyroid doses for the first 8 hours following the steam generator tube failure and the dose conversion factors are in .- Graduation Project: Simulation of a steam generator tube rupture in an Integrated Pressurized Water Reactor (iPWR) using RELAP5.

Courses: 1- Nuclear Reactors Thermal Hydraulics. 2- Nuclear reactor laboratory course: Neutronics experiments at Jordan Research and Training Reactor and Jordan Sub-Critical Assembly.

3- Nuclear Reactors : Currently enrolled in the Safe and .the steam generator tube rupture event in An enhanced inspection program was introduced to monitor the integrity of the whole steam generator closely.

Performance demonstration system for ultrasonic test (UT) and eddy current test (ECT) has also been initiated from Still, some alloy.