Development of thermal-hydraulic transient analysis code RETAC for AP1000 primary loop
- 1. Department of Nuclear Science and Technology, Xi'an Jiaotong University (China)
- 2. State Key Laboratory on Power Engineering and Multiphase Flow, Xi'an Jiaotong University (China)
Description
A thermal-hydraulic microcomputer code (RETAC, REactor Transient Analysis Code) for transient analysis of AP1000 primary loop was developed using FORTRAN language. The loss of flow accident (LOFA) was analyzed using FRTAC. Transient characteristics of some main system parameters were obtained, including the maximum fuel temperature and MDNBR in the hot channel, pressure and water level in the pressurizer and steam generator secondary side. The results show that at the early stage of the loss of flow accident, the highest fuel central temperature and MDNBR in the hot channel do not exceed specified limits and meet the safety criteria. Modular programming technique was adopted for RETAC and it is convenient for further modification and application. It is expected that the present work is instructive to develop Chinese own independent software for the design and safety analysis of large scale PWR. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 45
- Journal Issue
- 10
- Journal Page Range
- p. 1185-1190
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 45068387
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CHINA; COMPUTER CODES; DESIGN; FORTRAN; FUELS; HOT CHANNEL; LOSS OF FLOW; MODIFICATIONS; PRIMARY COOLANT CIRCUITS; PROGRAMMING; PWR TYPE REACTORS; R CODES; SAFETY ANALYSIS; STEAM GENERATORS; THERMAL HYDRAULICS; TRANSIENTS; WATER
- Descriptors DEC
- ACCIDENTS; ASIA; BOILERS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; PROGRAMMING LANGUAGES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs., 1 tabs., 11 refs.