Published August 1990 | Version v1
Journal article

BWRSAR calculations of reactor vessel debris pours for Peach Bottom short-term station blackout

  • 1. Oak Ridge National Lab., TN (USA). Boiling Water Reactor Severe Accident Technology (BWRSAT) Program

Description

This paper describes recent analyses performed by the BWR Severe Accident Technology (BWRSAT) Program at ORNL estimate the release of debris from the reactor vessel for the unmitigated short-term station blackout accident sequence. Calculations were performed with the BWR Severe Accident Response (BWRSAR) code and are based upon consideration of the Peach Bottom Atomic Power Station. The modeling strategies employed within BWRSAR for debris relocation within the reactor vessel are briefly discussed and the calculated events of the accident sequence, including details of the calculated debris pours, are presented. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
121
Journal Issue
3
Series
Nucl. Eng. Des.
Journal Page Range
327-339
ISSN
0029-5493
CODEN
NEDEA

Conference

Title
16. water reactor safety information meeting (WRSM-16).
Dates
24-28 Oct 1988.
Place
Gaithersburg, MD (USA).

Optional Information

Contract/Grant/Project number
Contract DOE 1886-8045-2B; DE-AC05-84OR21400