Published 2017 | Version v1
Miscellaneous

Simulations with trace of a BWR/4 steam line break under 'hot standby' conditions

Creators

  • 1. Paul Scherrer Inst., Villigen PSI (Switzerland)

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)

Part of:
Our nuclear future: renewal and responsibility. 37th Annual CNS conference and 41st CNS/CNA student conference

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.