抄録
A Detailed fuel rod design is carried out for the first time in the development of Supercritical-pressure Light Water Reactor (Super LWR). The fuel rod design is similar to that of LWR, consisting of UO2 pellets, a gas plenum and a Stainless Steel Cladding. The principle of rationalization of the criteria for anticipated transients of Super LWR is developed. The fuel rod failures can be conservatively prevented by limiting the cladding strain level within an elastic region, preventing the cladding buckling collapse, and keeping the pellet centerline temperature below its melting point. The FEMAXI-6 fuel analysis code of Japan Atomic Energy Research Institute (JAERI) is used to evaluate the fuel rod integrities in anticipated transient conditions. Detailed analyses have shown that allowable limits to the maximum fuel rod power and maximum cladding temperature can be determined to assure the fuel integrities. These limits may be useful in the plant safety analyses to confirm the fuel integrities during anticipated transients.
| 本文言語 | English |
|---|---|
| ページ | 2751-2758 |
| ページ数 | 8 |
| 出版ステータス | Published - 2005 |
| 外部発表 | はい |
| イベント | American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 - Seoul, Korea, Republic of 継続期間: 2005 5月 15 → 2005 5月 19 |
Other
| Other | American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 |
|---|---|
| 国/地域 | Korea, Republic of |
| City | Seoul |
| Period | 05/5/15 → 05/5/19 |
ASJC Scopus subject areas
- 原子力エネルギーおよび原子力工学
- 安全性、リスク、信頼性、品質管理