| Project/Area Number |
15H04230
|
|---|
| Research Category |
Grant-in-Aid for Scientific Research (B)
|
| Allocation Type | Single-year Grants |
|---|
| Section | 一般 |
|---|
| Research Field |
Nuclear fusion studies
|
|---|
| Research Institution | Kyushu University |
|---|
Principal Investigator |
|
|---|
| Co-Investigator(Kenkyū-buntansha) |
大塚 哲平 近畿大学, 理工学部, 准教授 (80315118)
片山 一成 九州大学, 総合理工学研究院, 准教授 (90380708)
|
|---|
| Co-Investigator(Renkei-kenkyūsha) |
GOTO MINORU 日本原子力研究開発機構, 原子力水素・熱利用研究センター, 研究主幹 (60414546)
NAKAGAWA SHIGEAKI 日本原子力研究開発機構, 原子力水素・熱利用研究センター, 研究主幹 (40414544)
|
|---|
| Research Collaborator |
NAKAYA HIROYUKI
KAWAMOTO YASUKO
KORA KAZUKI
NAGASUMI SATORU
IDA YUMA
OKAMOTO RYO
KOGA YUKI
SUGANUMA TAKURO
USHIDA HIROKI
|
|---|
| Project Period (FY) |
2015-04-01 – 2018-03-31
|
| Project Status |
Completed (Fiscal Year 2017)
|
| Budget Amount *help |
¥16,250,000 (Direct Cost: ¥12,500,000、Indirect Cost: ¥3,750,000)
Fiscal Year 2017: ¥4,030,000 (Direct Cost: ¥3,100,000、Indirect Cost: ¥930,000)
Fiscal Year 2016: ¥3,510,000 (Direct Cost: ¥2,700,000、Indirect Cost: ¥810,000)
Fiscal Year 2015: ¥8,710,000 (Direct Cost: ¥6,700,000、Indirect Cost: ¥2,010,000)
|
|---|
| Keywords | トリチウム / ジルコニウム / リチウム装荷体 / 高温ガス炉 / HTTR / 核融合炉 / リチウム装荷用ロッド / アルミナ / リチウム装荷ロッド / Li装荷用ロッド / 水素吸収 / Liロッド模擬試験体 / 核融合原型炉 / 同位体効果 / 酸素 |
|---|
| Outline of Final Research Achievements |
Heading on the demonstration of the tritium production using high-temperature gas-cooled reactor, tritium permeation experiment using the mockup of the Li-loading rod, which structured by Zr and Al2O3 tubes, was performed at 700 ℃ temperature. Tritium was kept being contained in the rod during 10 hours, which shows that the Li-loading rod has excellent tritium-containment performance. Other experiment showed that tritium-absorption performance of Zr is reduced in coexistence state of Zr and LiAlO2, but the performance can be recovered by using Ni coating on the Zr rod. An experimental procedure and test module were examined assuming future irradiation test in High Temperature engineering Test Reactor (HTTR). It was shown that almost 30 g of tritium can be produced in HTTR during 1 year operation.
|
