Simulation of Modified TRIGA-2000 with Plate-Type Fuel under LOFA Using EUREKA2/RR-Code
| Autor: | K.S. Sudjatmi, Ign. Djoko Irianto, Sukmanto Dibyo, Sihana Sihana |
|---|---|
| Rok vydání: | 2018 |
| Předmět: |
lofa transient
Nuclear and High Energy Physics Radiation Materials science eureka2/rr Nuclear engineering plate type fuel lcsh:TK9001-9401 Forced convection Coolant TRIGA Natural circulation Nuclear Energy and Engineering Nuclear reactor core Mass flow rate lcsh:Nuclear engineering. Atomic power Radiology Nuclear Medicine and imaging Research reactor Waste Management and Disposal triga-2000 Nucleate boiling |
| Zdroj: | Atom Indonesia, Vol 44, Iss 1, Pp 31-36 (2018) |
| ISSN: | 2356-5322 0126-1568 |
| DOI: | 10.17146/aij.2018.541 |
| Popis: | The TRIGA-2000 research reactor in Bandung, Indonesia, has operated for over 50 years. Recently, the problem of fuel availability arises, since its fuel is no longer produced. A modification of reactor core with new plate-type fuel has been suggested . The study of the neutronic assessment of plate-type fuel elements reactor core had been done. The next assessment that needed to be done was thermal-hydraulic analysis. The purpose of this study is to simulate the thermal-hydraulic characteristics of major parameters, such as reactor power, fuel cladding temperature, and departure from nucleate boiling ratio (DNBR) due to LOFA transient, using EUREKA2/RR code. During steady-state condition, downward flow forced convection mode for core coolant system is operated. The upward flow occurs when the natural circulation mode takes place. Hottest core channels temperature during LOFA conditions was considered. The reactor core was modeled as three channels, i . e ., the hottest channel, the average channel, and the channel for control assemblies, respectively. The s imulation was based on the steady-state condition of 2 M W t reactor power, cooling mass flow rate of 63.5 kg/s , and inlet coolant temperature to the core of 3 5.5 °C. The result shows that the hottest fuel cladding temperature does not cause a nucleate boiling. During LOFA, the residual heat was removed by natural circulation flow that occurred slowly. In order t o have larger inertia force , provision of the flywheel in the shaft of primary coolant pump is suggested. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|