Published December 2019 | Version v1
Journal article

TRACE simulations of IIST cooldown experiments

  • 1. Atomic Energy Council, Taoyuan City, Taiwan (China). Institute of Nuclear Energy Research
  • 2. Nuclear and New Energy Education and Research Foundation, HsinChu, Taiwan (China)
  • 3. National Tsing Hua University (China). Institute of Nuclear Engineering and Science

Description

IIST (Institute of Nuclear Energy Research Integral System Test) facility is a RHRP (Reduced-Height and Reduced-Pressure) facility for the three-loop PWR (Pressurized Water Reactor) NPP (Nuclear Power Plant) Maanshan. This test facility was established in 1992 for safety studies of the Maanshan NPP. TRACE is an advanced thermal hydraulic code which is still developed and updated by U.S. NRC. So, validation of specific models against experiments is still necessary. In this paper, cooldown experiments in IIST facility are used to validate the TRACE models. Additionally, the results of TRACE calculations are compared to results of RELAP5 calculations. This comparison shows that the calculations of TRACE are in good agreement to the data of IIST experiments and to the calculational results of RELAP5. So, TRACE can be used to simulate cooldown transients.

Additional details

Publishing Information

Journal Title
Kerntechnik (1987)
Journal Volume
84
Journal Issue
6
Journal Page Range
p. 508-519
ISSN
0932-3902
CODEN
KERNEU