Published 1985 | Version v1
Report Open

BWR program at ORNL - MELRPI code

Description

Since 1980, a series of accident studies concerning the Boiling Water Reactor (BWR) - MARK I containment plant design have been conducted by the Severe Accident Sequence Analysis (SASA) program at the Oak Ridge National Laboratory (ORNL). The SASA program is sponsored by Containment Systems Research Branch, Division of Accident Evaluation, United States Nuclear Regulatory Commission (USNRC). The program performs analysis in three major areas: plant response to operator actions before core uncovery; events from the onset of core uncovery through core melting, reactor vessel failure, and containment failure; and fission product release pathways, and the timing and magnitude of the releases. Analytical tools include the BWR-LTAS, MARCON2.OB, CORCON, TRENDS, Secondary Containment Model (SCM), and MELRPI computer codes. 2 refs., 2 figs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as TI85014648.

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
CONF-851115--6

Conference

Title
American Nuclear Society winter meeting.
Dates
10-15 Nov 1985.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17006971
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
B CODES; BWR TYPE REACTORS; C CODES; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; M CODES; REACTOR ACCIDENTS; SYSTEMS ANALYSIS; T CODES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS