Published March 2012 | Version v1
Miscellaneous

Steady state flow evaluations for passive auxiliary feedwater system of APR

  • 1. Korea Electric Power Corporation Engieering and Construction, Yongin (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

This paper briefly introduces a methodology to evaluate steady state flow of APR+ Passive Auxiliary Feedwater System (PAFS). The PAFS is being developed as a safety grade passive system to completely replace the existing active Auxiliary Feedwater System (AFWS). Natural circulation cooling can be generally classified into the single-phase, two-phase, and boiling-condensation modes. The PAF is designed to be operated in a boiling-condensation natural circulation mode. The steady-state flow rate should be equal to the steady-state boiling/condensation rate determined by the steady-state energy and momentum balances in the PAFS. The determined steady-state flow rate can be used in the design optimization for the natural circulation loop of the PAFS through the steady-state momentum balance. Since the retarding force, which is to be balanced by the driving force in the natural circulation system design depends on the reliable evaluation of the success of a natural circulation system design depends on the reliable evaluation of the pressure loss coefficients. In PAFS, the core decay heat is released by natural circulation flow between the S G secondary side and the Passive Condensation Heat Exchanger (PCHX) that is immersed in the Passive Condensation Cooling Tank (PCCT). The PCCT is located on the top of Auxiliary building The driving force is determined by the difference between the S/G (heat Source) secondary water level and condensation liquid (heat sink) level. It will overcome retarding force at flowrate in the system, which is determined by vaporization and condensation of the steam which is generated at the S/G by the latent heat in system. In this study, the theoretical method to estimate the steady state flow rate in boiling-condensation natural circulation system is developed and compared with test results

Part of:
Proceedings of the 18th Pacific Basin Nuclear Conference

Additional details

Publishing Information

Publisher
Pacific Nuclear Council
Imprint Place
La Grange Park (United States)
Imprint Title
Proceedings of the 18th Pacific Basin Nuclear Conference
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[9 p.]

Conference

Title
18. Pacific Basin Nuclear Conference
Acronym
PBNC 2012
Dates
18-23 Mar 2012
Place
Busan (Korea, Republic of)

INIS

Country of Publication
United States
Country of Input or Organization
Korea, Republic of
INIS RN
45032659
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; DESIGN; FEEDWATER; FLOW RATE; HEAT EXCHANGERS; NATURAL CONVECTION; PWR TYPE REACTORS; SAFETY
Descriptors DEC
CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; HYDROGEN COMPOUNDS; MASS TRANSFER; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 3 figs