Published October 1986
| Version v1
Miscellaneous
The Ginna tube-rupture event
Description
The R.E. Ginna steam generator tube rupture (SGTR) event on January 25, 1982 was simulated using the Transient Reactor Analysis code (TRAC), version TRAC-PF1/MOD1. A complete TRAC model of the Ginna plant was developed and the SGTR event was calculated to 5000 s. The overall plant behaviour was simulated with excellent to reasonable agreement obtained between calculated results and measured data. A primary objective of calculating and matching the actual reactor trip time was achieved. The Ginna SGTR event provided a meaningful plant-transient benchmark for reactor-safety thermal-hydraulic computer codes. The analysis presented demonstrates that TRAC can accurately simulate full-scale plant SGTR transients
Additional details
Additional titles
- Subtitle (English)
- A plant-transient benchmark for TRAC
Publishing Information
- ISBN
- 0-010784-11-9
- Imprint Title
- Proceedings of the 2. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 950 p.
- Journal Page Range
- p. 96-118.
- Report number
- INIS-mf--12868(v.1,2)
Conference
- Title
- 2. International conference on simulation methods in nuclear engineering.
- Dates
- 14-16 Oct 1986.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 22063882
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; GINNA-1 REACTOR; MEDIUM PRESSURE; REACTOR SHUTDOWN; RUPTURES; STEAM GENERATORS; T CODES; TRANSIENTS; TUBES
- Descriptors DEC
- BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SHUTDOWN; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS