Published October 2016 | Version v1
Journal article

Simulation of containment pressurization in a large break-loss of coolant accident using single-cell and multicell models and CONTAIN code

  • 1. Reactor Research School, Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of)
  • 2. Faculty of Engineering, Shahid Beheshti University, Tehran (Iran, Islamic Republic of)

Description

Since the inception of nuclear power as a commercial energy source, safety has been recognized as a prime consideration in the design, construction, operation, maintenance, and decommissioning of nuclear power plants. The release of radioactivity to the environment requires the failure of multiple safety systems and the breach of three physical barriers: fuel cladding, the reactor cooling system, and containment. In this study, nuclear reactor containment pressurization has been modeled in a large break-loss of coolant accident (LB-LOCA) by programming single-cell and multicell models in MATLAB. First, containment has been considered as a control volume (single-cell model). In addition, spray operation has been added to this model. In the second step, the single-cell model has been developed into a multicell model to consider the effects of the nodalization and spatial location of cells in the containment pressurization in comparison with the single-cell model. In the third step, the accident has been simulated using the CONTAIN 2.0 code. Finally, Bushehr nuclear power plant (BNPP) containment has been considered as a case study. The results of BNPP containment pressurization due to LB-LOCA have been compared between models, final safety analysis report, and CONTAIN code's results

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
48
Journal Issue
5
Series
14 refs, 18 figs, 2 tabs
Journal Page Range
p. 1140-1153
ISSN
1738-5733

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47121252
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
C CODES; CONTAINMENT; DECOMMISSIONING; DESIGN; LOSS OF COOLANT; MAINTENANCE; NUCLEAR POWER PLANTS; PRESSURIZATION; SAFETY; SIMULATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; THERMAL POWER PLANTS