Published May 2012 | Version v1
Miscellaneous

Use of the MARS-KS Code for the Prediction of Condensation Heat Transfer in a Passive Cooling Heat Exchanger

  • 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

The Passive Auxiliary Feedwater System (PAFS) is new conceptual design of auxiliary feedwater system in APR+ nuclear power plan. Although PAFS is relatively a simple system composed of one heat exchanger and several valves, it is designed to be capable of performing safety functions of which the conventional Auxiliary Feedwater System (AFS) did by active components. Furthermore, PAFS carry out safety functions during the period of the total loss of electrical power (i.e. SBO). PAFS provides cooling water into a steam generator to remove the residual heat under transient and accident conditions. During operation of PAFS, the phase change occurs at the Passive Cooling Heat Exchanger (PCHX) which located at the inside of the Passive Condensation Cooling Tank (PCCT). Then, the condensate water flows into the steam generator by gravity and it evaporates in the steam generator again. Therefore, the characteristics of heat transfer inside the PCHX is a main issue of PAFS. The schematic diagram of PAFS is in Figure 1. This paper addresses a preliminary investigation of the applicability of the thermal-hydraulic system analysis code 'MARS-KS' for predicting the thermalhydraulic characteristics of PCHX and PCCT in the PAFS. In addition, the heat transfer performance of PCHX during operational transients has been investigated

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 spring meeting of the KNS
Dates
16-18 May 2012
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
43073577
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; DESIGN; EMERGENCY PLANS; FEEDWATER; HEAT EXCHANGERS; HEAT TRANSFER; M CODES; PERFORMANCE; PWR TYPE REACTORS; SAFETY; STEAM GENERATORS; VALVES
Descriptors DEC
BOILERS; COMPUTER CODES; CONTROL EQUIPMENT; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 5 figs