Response of BWR Mark III containments to short-term station blackout severe accident sequences



Publisher: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC

Written in English
Published: Pages: 320 Downloads: 21
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Subjects:

  • Boiling water reactors -- Accidents.,
  • Nuclear reactors -- Containment -- Safety measures.

Edition Notes

Statementprepared by S.R. Greene ... [et al.] ; prepared for Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
ContributionsGreene, Sherrell R., Oak Ridge National Laboratory., U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.
The Physical Object
Paginationxxii, 320 p. :
Number of Pages320
ID Numbers
Open LibraryOL14679862M

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Response of BWR Mark III containments to short-term station blackout severe accident sequences Download PDF EPUB FB2

This report describes the results of a series of calculations conducted to investigate the response of BWR Mark 2 containments to short-term and long-term station blackout severe accident sequences. The BWR-LTAS, BWRSAR, and MELCOR codes were employed to conduct quantitative accident sequence progression and containment response analyses for several station blackout.

Get this from a library. The Response of BWR Mark III containments to short-term station blackout severe accident sequences. [Sherrell R Greene; Oak Ridge National Laboratory.; U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.;].

Juan Carbajo and Sherrell R. Greene, Containment Failure Time and Mode for a Low-Pressure Short-Term Station Blackout in a BWR-4 with Mark-III Containment, Proceedings of the American Nuclear Society Winter Meeting, San Francisco, CA, November At the time of this evaluation in Februarythere were 9 BWRs with MARK II containments located at 6 sites.

The geometry of the reactor pedestal support and downcomers has a major impact on the performance of the containment, if the reactor vessel fails in a severe accident.

Loss of Coolant Accident (LOCA), limiting according to the discharge to drywell in the short term with ft 2 break size. • Station Blackout (SBO), a total loss of outer and inner alternating current, limiting regarding to the discharge through the SRVs to by: 8.

The response of BWR Mark III containments to short-term station blackout severe accident sequences Article Investigation of drywell flooding at the Browns Ferry Nuclear Plant. Juan Carbajo and Sherrell R. Greene, Containment Failure Time and Mode for a Low-Pressure Short-Term Station Blackout in a BWR-4 with Mark-III Containment, Proceedings of the American Nuclear Society Winter Meeting, San Francisco, CA, November 3.

During the early phase of a nuclear accident, the EPA Protective Action Guide (PAG) for evacuation or sheltering of the public is A rem B.

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Explain why the larvae moved to a range of different positions. Use a heat filter or don't place the lamp too close to the larvae to ensure the response isn't due to the heat of the lamp. Stress tests performed in Europe after accident at Fukushima Daiichi also required evaluation of the consequences of loss of safety functions due to station blackout (SBO).

Long-term SBO in a pressurized water reactor (PWR) leads to severe accident sequences, assuming that existing plant means (systems, equipment, and procedures) are used for accident by: 9. The BWR long-term station blackout accident has been analysed using TRAC-BF1.

The reactor pressure, the core liquid level and the dry well pressure were shown to be in good agreement with the observed data at the unit 2 reactor of the Fukushima Daiichi nuclear power by: Request PDF | Influence of the wet-well nodalization of a BWR3 Mark I on the containment thermal-hydraulic response during an SBO accident | In the field of severe accidents simulation one of the.

A significance determination process (SDP) is proposed that assigns risk characterization to inspection findings based on large early release frequency (LERF) considerations. This process is designed to interface directly with the SDP that is based on findings related to those structures, systems, and components (SSCs) that can influence the core damage frequency (CDF).

The relatively small size of these containments presents accident mitigation issues that are generally similar to those for BWR Mark III plants. The primary focus of containment mitigating strategies to comply with Order EA for ice condenser plants is provision of alternative means to restore the containment cooling and spray functions.

An assessment of BWR (boiling water reactor) Mark-II containment challenges, failure modes, and potential improvements in performance Technical Report. This report assesses challenges to BWR Mark II containment integrity that could potentially arise from severe accidents.

ice condenser and BWR Mark III containments. For station blackout (SBO) events in which neither preferred AC nor backup AC power provided by the emergency diesel generators would be available, the igniters would not be functioning and containment integrity could be challenged.

The proposed system enhancement is to provide an additional independent power. Operator Response to Station Black Out Plant recovery from SBO: • Only possible by restoring AC power • In the meantime: Minimize RCS inventory loss Objective (as defined by US NRC): Ensure SBO Coping Time of 4 to 8 hours Operator actions: 1) Limit loss of RCS coolant: Close primary PORV, letdown 2) Limit loss of SG coolant:File Size: 1MB.

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Contain calculations of debris conditions adjacent to the BWR Mark I drywell shell during the later phases of a severe accident Nuclear Engineering and Design 3 2-s 23 IAEA.

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“IA- is an occurrence in an industrial premises causing physical injury to an. Washington, DC: The National Academies Press. doi: / The containment serves as a barrier to the release of radioactive material to the environment during a severe accident (Sidebar ).

BWR Mark III containments are not inerted. They have hydrogen control systems that are designed to burn hydrogen at low concentrations. Additional guidance concerning the availability of deliberate ignition systems during station blackout sequences is being developed as part of the staff's review of Generic Safety Issue “Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident.”.

5 Lessons Learned: Plant Operations and Safety Regulations. The final three chapters of this report are intended to address the third and fourth charges of the study task (see Sidebar in Chapter 1): • Lessons that can be learned from the accident to improve commercial nuclear plant safety and security systems and operations.

Additional guidance concerning the availability of deliberate ignition systems during station blackout sequences is being developed as part of the staff's review of Generic Safety Issue “Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident.” Back to Citation.

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