skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios

Abstract

The direct Containment Heating (DCH) calculations require that the transient rate at which the melt is ejected from the reactor cavity during hypothetical pressurized melt ejection accident scenarios be calculated. However, at present no models, that are able to predict the available melt dispersal data from small scale reactor cavity models, are available. In this report, a simple idealized model of the melt dispersal process within a reactor cavity during a pressurized melt ejection accident scenario is presented. The predictions from the model agree reasonably well with the integral data obtained from the melt dispersal experiments using a small scale model of the Surry reactor cavity. 17 refs., 15 figs.

Authors:
Publication Date:
Research Org.:
Brookhaven National Lab. (BNL), Upton, NY (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
5703178
Report Number(s):
BNL-46305
ON: DE91015520
DOE Contract Number:  
AC02-76CH00016
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; CORIUM; FLUID FLOW; FLUID MECHANICS; MELTDOWN; CONTAINMENT; NUCLEAR POWER PLANTS; C CODES; CAVITIES; HEAT TRANSFER; HEATING; HYDRAULICS; MATHEMATICAL MODELS; PRESSURE VESSELS; REACTOR SAFETY; SCALE MODELS; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; TRANSIENTS; ACCIDENTS; COMPUTER CODES; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 990200 - Mathematics & Computers

Citation Formats

Tutu, N K. An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios. United States: N. p., 1991. Web. doi:10.2172/5703178.
Tutu, N K. An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios. United States. https://doi.org/10.2172/5703178
Tutu, N K. 1991. "An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios". United States. https://doi.org/10.2172/5703178. https://www.osti.gov/servlets/purl/5703178.
@article{osti_5703178,
title = {An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios},
author = {Tutu, N K},
abstractNote = {The direct Containment Heating (DCH) calculations require that the transient rate at which the melt is ejected from the reactor cavity during hypothetical pressurized melt ejection accident scenarios be calculated. However, at present no models, that are able to predict the available melt dispersal data from small scale reactor cavity models, are available. In this report, a simple idealized model of the melt dispersal process within a reactor cavity during a pressurized melt ejection accident scenario is presented. The predictions from the model agree reasonably well with the integral data obtained from the melt dispersal experiments using a small scale model of the Surry reactor cavity. 17 refs., 15 figs.},
doi = {10.2172/5703178},
url = {https://www.osti.gov/biblio/5703178}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Jun 01 00:00:00 EDT 1991},
month = {Sat Jun 01 00:00:00 EDT 1991}
}