2022 Fiscal Year Final Research Report
Experimental evaluation of neutron transport and fuel production in fusion blanket
| Project/Area Number |
20K14442
|
|---|
| Research Category |
Grant-in-Aid for Early-Career Scientists
|
| Allocation Type | Multi-year Fund |
|---|
| Review Section |
Basic Section 14020:Nuclear fusion-related
|
|---|
| Research Institution | Kyoto University |
|---|
Principal Investigator |
Mukai Keisuke 京都大学, エネルギー理工学研究所, 助教 (70807700)
|
|---|
| Project Period (FY) |
2020-04-01 – 2023-03-31
|
| Keywords | 核融合中性子 / 燃料生産性 / ブランケット / コーティング / 中性子発生 / オンライン計測 |
|---|
| Outline of Final Research Achievements |
In this study, a compact discharge fusion neutron source was used to generate spectral neutrons with a wide energy range, and the neutron and tritium production rates were measured. The electrodes were coated with titanium to increase the neutron production rate. This coating increased the neutron generation rate by about 40%, and depth analysis of the electrodes revealed that the increased surface concentration of deuterium contributed to the increased neutron production rate. Neutron irradiation experiments were conducted with a CVD single-crystal diamond detector placed at five different positions (positions A-E) under discharge conditions of 9 mA and 60 kV. Tritons produced by the capture reaction of lithium were detected, and the tritium production rate was experimentally evaluated. It was shown that the tritium production rate can be evaluated with high accuracy using a small discharge neutron source.
Translated with www.DeepL.com/Translator (free version)
|
| Free Research Field |
中性子工学
|
| Academic Significance and Societal Importance of the Research Achievements |
本研究では、電極表面へのコーティングによって中性子発生率が上昇することを示した。中性子を用いた建築物の診断やラジオグラフィなどの応用に向け、小型中性子源の高性能化に寄与する成果であると考えられる。中性子輸送実験ではモンテカルロ計算との比較により、C/E値（実験値と計算値の比）と測定誤差の評価を行った。線量の低い小型中性子源を用いて三重水素生成率を評価したのは本研究がはじめてであり、高コストな加速器を使用しない実験手法として、ブランケット試験体の燃料生産性能の評価に役立つと考えられる
|
