Abstract
An equilibrium core of High Temperature Supercritical-pressure Light Water Reactor, now called Super LWR, has been designed. The fuel assemblies loaded in the peripheral region of the core are cooled with descending flow to achieve a high average coolant core outlet temperature. In the present design, Stainless Steel is used for fuel rod claddings and for structural materials. Gd 2O3 concentration and the fuel load pattern are optimized to reduce fuel enrichment. Watts correlations are used for prediction of heat transfer in the core, which takes into account an improvement of heat transfer for downward flow, different from the Oka-Koshizuka correlation used in the previous design. It is found that the water rods with their downward flow need to be thermally insulated with thin ZrO2 layer to keep the moderator temperature below the pseudo critical temperature. As a result, an average coolant core outlet temperature of 500C is achieved. In addition, the effect of various heat transfer correlations on the cladding surface temperature is evaluated.
| Original language | English |
|---|---|
| Pages | 2711-2720 |
| Number of pages | 10 |
| Publication status | Published - 2005 Dec 1 |
| Externally published | Yes |
| Event | American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 - Seoul, Korea, Republic of Duration: 2005 May 15 → 2005 May 19 |
Other
| Other | American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 |
|---|---|
| Country/Territory | Korea, Republic of |
| City | Seoul |
| Period | 05/5/15 → 05/5/19 |
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality