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Containment severe accident thermohydraulic phenomena

Technical Report:

Abstract

This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phenomenological knowledge, including an account of relevant experimental investigations and to discuss, to some extent, the modelling approach used in the MAAP 3.0 computer code. The MAAP code has been used in Sweden as the main tool in the analysis of severe accidents. The dependence of the containment accident progression and containment phenomena on the initial conditions, which in turn are heavily dependent on the in-vessel accident progression and phenomena as well as associated uncertainties, is emphasized. The report is in three parts dealing with: * Swedish reactor containments, the severe accident mitigation programme in Sweden and containment accident progression in Swedish PWRs and BWRs as predicted by the MAAP 3.0 code. * Key non-energetic ex-vessel phenomena (melt fragmentation in water, melt quenching and coolability, core-concrete interaction and high temperature in containment). * Early containment threats due to energetic events (hydrogen combustion, high pressure melt ejection and direct containment heating, and ex-vessel steam explosions). The report concludes that our understanding of the containment severe accident  More>>
Authors:
Frid, W [1] 
  1. Swedish Nuclear Power Inspectorate, Stockholm (Sweden)
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
RAMA-III-89-04
Reference Number:
SCA: 220504; 210000; PA: AIX-24:001009; SN: 93000912995
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; CONCRETES; CONTAINERS; CONTAINMENT SYSTEMS; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FUEL-COOLANT INTERACTIONS; HIGH PRESSURE; MOLTEN METAL-WATER REACTIONS; REACTOR SAFETY; THERMODYNAMICS; 220504; 210000; DESIGN BASIS AND HYPOTHETICAL ACCIDENTS; NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
OSTI ID:
10110221
Research Organizations:
Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Swedish Radiation Protection Inst., Stockholm (Sweden); Swedish State Power Board, Vaellingby (Sweden); Oskarshamnsverkets Kraftgrupp AB, Stockholm (Sweden); Sydkraft AB, Malmoe (Sweden)
Country of Origin:
Sweden
Language:
English
Other Identifying Numbers:
Other: ON: DE93609206; TRN: SE9200322001009
Availability:
OSTI; NTIS; INIS
Submitting Site:
SWDN
Size:
[151] p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Frid, W. Containment severe accident thermohydraulic phenomena. Sweden: N. p., 1991. Web.
Frid, W. Containment severe accident thermohydraulic phenomena. Sweden.
Frid, W. 1991. "Containment severe accident thermohydraulic phenomena." Sweden.
@misc{etde_10110221,
title = {Containment severe accident thermohydraulic phenomena}
author = {Frid, W}
abstractNote = {This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phenomenological knowledge, including an account of relevant experimental investigations and to discuss, to some extent, the modelling approach used in the MAAP 3.0 computer code. The MAAP code has been used in Sweden as the main tool in the analysis of severe accidents. The dependence of the containment accident progression and containment phenomena on the initial conditions, which in turn are heavily dependent on the in-vessel accident progression and phenomena as well as associated uncertainties, is emphasized. The report is in three parts dealing with: * Swedish reactor containments, the severe accident mitigation programme in Sweden and containment accident progression in Swedish PWRs and BWRs as predicted by the MAAP 3.0 code. * Key non-energetic ex-vessel phenomena (melt fragmentation in water, melt quenching and coolability, core-concrete interaction and high temperature in containment). * Early containment threats due to energetic events (hydrogen combustion, high pressure melt ejection and direct containment heating, and ex-vessel steam explosions). The report concludes that our understanding of the containment severe accident progression and phenomena has improved very significantly over the parts ten years and, thereby, our ability to assess containment threats, to quantify uncertainties, and to interpret the results of experiments and computer code calculations have also increased. (au).}
place = {Sweden}
year = {1991}
month = {Aug}
}