Preliminary Study on the Cooling Performance of Passive Emergency Core Cooling System
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The H-SIT ensures emergency coolant injection into the core in the high-pressure region between the reactor coolant system (RCS) operation pressure (15.0 MPa) and the MP-SIT operation pressure (4.2 MPa). While its tank design is identical to that of a conventional SIT, the upper part of the tank and the cold leg are connected with a pressure balancing line (PBL), and the gravity-driven injection of cooling water from the tank into the reactor takes place at high pressure. In this study, an integral effect test (IET) was conducted on a loss of coolant accident (LOCA), which requires the operation of the primary makeup system, in order to confirm the performance of each PECCS component. A LOCA is an accident caused by a pipe break in the reactor coolant pressure boundary that results in a loss of reactor coolant at a rate in excess of the capability of a normal reactor coolant makeup system. A classic small break LOCA (SBLOCA) scenario with a break area of 0.024 square feet (two-inch break) was selected for PECCS performance analysis. In this study, the simulation of transient accident was performed on the two-inch cold leg break selected from the ATLAS-based SBLOCA scenarios to assess the cooling performance of the passive emergency core cooling system. The H-SIT (SITs #1 and #3) injection starts successfully at the moment when the primary side pressure falls to 10.0 MPa, and the MP-SIT (SITs #2 and #4) injection starts when the pressure falls further to 4.21 MPa. The operation condition such as PCT for ADVs #1 – #4 constituting the auto depressurization system (ADS) needs to be added.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059470
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLING; COOLING SYSTEMS; DAMAGE; DESIGN; LOSS OF COOLANT; PERFORMANCE; SAFETY INJECTION; TANKS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENERGY SYSTEMS; REACTOR ACCIDENTS
Optional Information
- Notes
- 1 refs, 4 figs, 1 tab