Abstract
During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.
| Original language | English |
|---|---|
| Pages (from-to) | 69-80 |
| Number of pages | 12 |
| Journal | Nuclear Engineering and Design |
| Volume | 150 |
| Issue number | 1 |
| DOIs | |
| Publication status | Published - Sep 2 1994 |
| Externally published | Yes |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering