Status of TRAC-PF1/MOD1 independent assessment at Sandia
Description
Sandia's TRAC-PF1/MOD1 independent assessment program is part of a multi-faceted effort sponsored by the NRC to determine the ability of various systems codes to predict the detailed thermal/hydraulic response of LWRs during accident and off-normal conditions. TRAC-PF1/MOD1 is being assessed against test data from various integral and separate effects experimental facilities. Results from our PKL natural circulation, NEPTUNUS pressurizer, B and W OTSG, Northwestern University condensing flow, and LOBI large break A1-04R and intermediate break B-RIM test analyses were reported at least year's WRSRIM; this paper presents the results of more recent work for Northwestern University perforated-plate CCFL, Dartmouth vertical tube countercurrent flow, LOFT large break L2-5, and Semiscale intermediate break S-IB-3, feedwater line break S-SF-3 and steamline break S-SF-5 tests. In the course of our TRAC-PF1/MOD1 assessment calculations, a number of coding, documentation and modeling inadequacies have been identified and reported to the code developers at LANL
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as TI86001913.
Files
Additional details
Publishing Information
- Imprint Pagination
- 23 p.
- Report number
- SAND--85-1829C
Conference
- Title
- 13. water reactor safety research information meeting.
- Dates
- 22-25 Oct 1985.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17028394
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; PERFORMANCE; REACTOR ACCIDENTS; T CODES; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; REACTORS
Optional Information
- Secondary number(s)
- CONF-8510173--3.