Simulations with trace of a BWR/4 steam line break under 'hot standby' conditions
Description
Simulations have been performed with TRACE (V5.0P1) to predict the behavior of a BWR/4 plant under 'Hot-standby' conditions and subjected to a steam line break in the turbine building, which has no provision for radioactivity barriers. Two break sizes were considered, a 10% and 200% ('guillotine') break, along with two main steam isolation valve closure durations, 5 seconds and 20 seconds. Thus, three transients embodying a combination of these conditions have been simulated. The transients initiated from a system pressure P=68 bars and 5% core power, while the water level was at +1.15 m. The results yielded a total discharged mass of water and steam bounded between 1380 kg and 6730 kg for the limiting cases of the 10% break with 5 seconds closure time and the 200% break with 10 seconds closure time, respectively. The worst-case scenario result is consistent with the conservative (SAR) value of 7575 kg. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 978-1-926773-24-7
- Imprint Title
- Our nuclear future: renewal and responsibility. 37th Annual CNS conference and 41st CNS/CNA student conference
- Imprint Pagination
- 408 Megabytes
- Journal Page Range
- [10 p.]
Conference
- Title
- 37. annual Canadian Nuclear Society conference; 41. CNS/CNA student conference
- Dates
- 4-7 Jun 2017
- Place
- Niagara Falls, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 50008944
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; SIMULATION; STEAM LINE BREAK ACCIDENTS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs., 4 tabs., 10 figs.