Assessment of Condensation Heat Transfer Models of TRACE V5.0 Patch 5 Using PASCAL Tests (NUREG/IA-0534)

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Publication Information

Manuscript Completed: May 2022
Date Published: September 2022

Prepared by:
Kyung-Won Lee*, Aeju Cheong*, Andong Shin*, Jae Soon Kim*, Kyoung-Ho Kang**

*Korea Institute of Nuclear Safety (KINS)
62 Gwahak-ro, Yuseong-gu,
Daejeon 34142, Republic of Korea

**Korea Atomic Energy Research Institute (KAERI)
111 Daedeok-daero 989beon-gil, Yuseong-gu,
Daejeon 34057, Republic of Korea

K. Tien, NRC Project Manager

Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared as part of
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Availability Notice

Abstract

The passive auxiliary feedwater system (PAFS) is one of the advanced safety features of the Advanced Power Reactor Plus (APR+) and Advanced Power Reactor 1000 (APR1000). During a plant transient, the PAFS cools down the secondary side of the steam generator, and removes the decay heat of the reactor core by condensing steam in nearly-horizontal U-shaped tubes submerged inside the passive condensation cooling tank. This study investigated the predictive capability of TRACE V5.0 patch 5 for the cooling and operational performance of the PAFS. For this purpose, the predictive capability of the code for the condensing heat transfer in the horizontal stratified flow was assessed using the results of a PASCAL experiment. The filmwise condensation heat transfer model and horizontal stratified condensation model of TRACE were evaluated. In addition, a new condensation model developed by Pusan National University (PNU model) was implemented and evaluated. The filmwise condensation heat transfer model and horizontal stratified condensation model generally overestimated the pressure and the steam flow rate of the steam generator. The PNU condensation model, on the other hand, predicted well the pressure and the steam flow rate of the steam generator under various heater powers.