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.Files
17006971.pdf
Files
(119.3 kB)
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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