Published December 2014 | Version v1
Journal article

An analysis on the severe accident progression with operator recovery actions

  • 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.2014.09.023

Additional 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.