An analysis on the severe accident progression with operator recovery actions
Creators
- 1. Korea University of Science and Technology (UST), 217 Gajeong-ro, Yuseong-gu, Daejeon 305-333 (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejon 305-353 (Korea, Republic of)
Description
Highlights: • Severe accident progression for the station blackout and SBLOCA accident. • Analyses on APR1400 using MELCOR. • Operator recovery actions for decay heat removal and inventory make up. • Determine the time allowed for the operator to prevent reactor vessel failure. • Insight for the operator recovery actions for the severe accident management. - Abstract: Analyses on the severe accident progressions for the station blackout (SBO) accident and small break LOCA (SBLOCA) initiated severe accident were performed for APR1400 by using MELCOR computer code. Operator recovery actions for decay heat removal and inventory make up using a depressurization system and safety injection pump were simulated in parallel with a simulation of the severe accident progression. Sensitivity studies on the operator actions were performed to investigate the changes in the timing of the reactor vessel failure and to determine the time allowed for the operator to prevent reactor vessel failure. Sensitivity analyses on the effect of major modeling parameters were performed additionally to quantify the uncertainties in timing. It is found that the operator has about 2 h for the recovery actions after the indication of core damage by the signal of core exit thermocouple (CET) for the SBLOCA initiated severe accident, while the operator has to take immediate actions after the indication of core damage by CET for the SBO accident
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2014.09.023Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2014.09.023;
- PII
- S0029-5493(14)00534-2;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 280
- Journal Page Range
- p. 429-439
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46100806
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENT MANAGEMENT; AFTER-HEAT REMOVAL; COMPUTER CODES; DAMAGE; DEPRESSURIZATION SYSTEMS; FAILURES; LOSS OF COOLANT; REACTOR VESSELS; SAFETY INJECTION; SENSITIVITY ANALYSIS; SIGNALS; SIMULATION
- Descriptors DEC
- ACCIDENTS; CONTAINERS; MANAGEMENT; REACTOR ACCIDENTS; REMOVAL
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.