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
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 51004655
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLING; MAANSHAN-1 REACTOR; MAANSHAN-2 REACTOR; PRIMARY COOLANT CIRCUITS; REACTOR CORES; T CODES; TEST FACILITIES; THERMAL HYDRAULICS; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS