Published May 2018 | Version v1
Miscellaneous

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.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

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