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