A Severe Accident Analysis for the System-Integrated Modular Advanced Reactor

Title
A Severe Accident Analysis for the System-Integrated Modular Advanced Reactor
Authors
제무성
Keywords
ACCIDENT MANAGEMENT; COMPUTERIZED SIMULATION; CONTAINMENT BUILDINGS; CONTAINMENT SPRAY SYSTEMS; LOSS OF COOLANT; M CODES; MODULAR STRUCTURES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; REPUBLIC OF KOREA; STEADY-STATE CONDITIONS; SURFACE AREA
Issue Date
2015-03
Publisher
INFORUM VERLAGS-VERWALTUNGSGESELLSCHAFT MBH
Citation
ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, v. 60, NO 3, Page. 173-182
Abstract
The System-Integrated Modular Advanced Reactor (SMART) that has been recently designed in KOREA and has acquired standard design certification from the nuclear power regulatory body (NSSC) is an integral type reactor with 330MW thermal power. It is a small sized reactor in which the core, steam generator, pressurizer, and reactor coolant pump that are in existing pressurized light water reactors are designed to be within a pressure vessel without any separate pipe connection. In addition, this reactor has much different design characteristics from existing pressurized light water reactors such as the adoption of a passive residual heat removal system and a cavity flooding system. Therefore, the safety of the SMART against severe accidents should be checked through severe accident analysis reflecting the design characteristics of the SMART. For severe accident analysis, en analysis model has been developed reflecting the design information presented in the standard design safety analysis report. The severe accident analysis model has been developed using the MELCOR code that is widely used to evaluate pressurized LWR severe accidents. The steady state accident analysis model for the SMART has been simulated. According to the analysis results, the developed model reflecting the design of the SMART is found to be appropriate. Severe accident analysis has been performed for the representative accident scenarios that lead to core damage to check the appropriateness of the severe accident management plan for the SMART The SMART has been shown to be safe enough to prevent severe accidents by utilizing severe accident management systems such as a containment spray system, a passive hydrogen recombiner, and a cavity flooding system. In addition, the SMART is judged to have been technically improved remarkably compared to existing PWRs. The SMART has been designed to have a larger reactor coolant inventory compared to its core's thermal power, a large surface area in the lower hemisphere of the reactor pressure vessel assembly, and a large free volume in the containment building.
URI
http://hdl.handle.net/20.500.11754/24037https://inis.iaea.org/search/search.aspx?orig_q=RN:46063038
ISSN
1431-5254
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
Files in This Item:
There are no files associated with this item.
Export
RIS (EndNote)
XLS (Excel)
XML


qrcode

Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.

BROWSE