Published 1992 | Version v1
Report Restricted

Modelling steam explosions for the Savannah River Site reactor probabilistic risk assessment

  • 1. Westinghouse Savannah River Co., Aiken, SC (United States)
  • 2. Science Applications International Corp., Albuquerque, NM (United States)

Description

As part of the probabilistic risk assessment (PRA) for the Savannah River Site (SRS) reactors, a theoretical model has been used to evaluate the magnitude of steam explosions that could occur during postulated severe accidents at the plant. The model predicts pressure, steam generation and mechanical work during the explosion phase of the interaction. The model is applied to two hypothetical events illustrating typical small-scale and large-scale explosions found in the PRA. These two examples show that yield predictions may range from megajoules to gigajoules for kinetic energy, 10 to 1000 kg for steam generated, and 10 to 1000 atm for peak explosion-zone pressures. A brief study is made to characterize the sensitivity of kinetic energy yield to initial fuel mass and fuel temperature. Explosion kinetic energy increases linearly in proportion to fuel mass, but displays a non-linear dependence on fuel temperature over parameter values of interest

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE93005069; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Additional titles

Subtitle (English)
Revision 1

Publishing Information

Imprint Pagination
6 p.
Report number
WSRC-MS--92-387-Rev.1

Conference

Title
Probabilistic safety assessment international topical meeting (PSA 93).
Dates
27-29 Jan 1993.
Place
Clearwater Beach, FL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24047840
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; CORIUM; EXPLOSIONS; FUEL ELEMENTS; HEAT TRANSFER; MATHEMATICAL MODELS; PRODUCTION REACTORS; REACTOR SAFETY; RISK ASSESSMENT; SAVANNAH RIVER PLANT; STEAM
Descriptors DEC
ENERGY TRANSFER; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTORS; SAFETY; US AEC; US DOE; US ERDA; US ORGANIZATIONS

Optional Information

Contract/Grant/Project number
Contract AC09-89SR18035
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-930116--31-Rev.1.