编辑: 此身滑稽 | 2019-07-15 |
72 h at a full power of about
10 MW and the steady-state operation experiment was conducted during this period. The main operational parameters as well as the corresponding design values of the HTR-10 are listed in Table 1. It can be observed that the basic technical speci?- cations meet the design requirements very well. In addition, experimental data were obtained for validation of the ther- mal-hydraulic models and codes used by INET. Within the framework of a Coordinated Research Project on Evaluation of HTGR Performance (CRP-5) initiated by the International Atomic Energy Agency (IAEA), the calcu- lation of steady-state temperature distribution of the HTR-10 under experimental operation with a full power initial core (FPIC) has been de?ned as one of the benchmark problems related to HTGR thermal hydraulics analysis. The CRP-5 was launched by the Technical Working Group on Gas- Cooled Reactors (TWG-GCR) of IAEA in 1997, with the objective of validating existing HTGR calculation codes for reactor physics and thermal hydraulics by checking them against each other and against available........