Project/Area Number |
16206095
|
Research Category |
Grant-in-Aid for Scientific Research (A)
|
Allocation Type | Single-year Grants |
Section | 一般 |
Research Field |
Nuclear engineering
|
Research Institution | Tokyo Institute of Technology |
Principal Investigator |
FUJII Yasuhiko Research Lab. Nuclear Reactors, Professor, 原子炉工学研究所, 教授 (20016869)
|
Co-Investigator(Kenkyū-buntansha) |
IKEDA Yasuhisa Research Lab. Nuclear Reactors, Associate Professor, 原子炉工学研究所, 助教授 (40323836)
NOMURA Masao Research Lab. Nuclear Reactors, Assistant Professor, 原子炉工学研究所, 助手 (60100997)
HARADA Masayuki Research Lab. Nuclear Reactors, Assistant Professor, 原子炉工学研究所, 助手 (20156516)
SUZUKI Tatsuya Research Lab. Nuclear Reactors, Assistant Professor, 原子炉工学研究所, 助手 (70323839)
|
Project Period (FY) |
2004 – 2006
|
Project Status |
Completed (Fiscal Year 2006)
|
Budget Amount *help |
¥50,310,000 (Direct Cost: ¥38,700,000、Indirect Cost: ¥11,610,000)
Fiscal Year 2006: ¥8,190,000 (Direct Cost: ¥6,300,000、Indirect Cost: ¥1,890,000)
Fiscal Year 2005: ¥15,600,000 (Direct Cost: ¥12,000,000、Indirect Cost: ¥3,600,000)
Fiscal Year 2004: ¥26,520,000 (Direct Cost: ¥20,400,000、Indirect Cost: ¥6,120,000)
|
Keywords | Isotope separation / Reprocessing / Ion exchange / Chromatography / Nitride fuel / Inherent safe / クロマトグラフィ |
Research Abstract |
Nitride fuel has promising characteristics, such as high melting point, high thermal conductivity, high breeding ratio etc. However, the natural nitrogen cannot be used because the major isotope ^<14>N adsorbs neutrons, resulting in generation of radioactive ^<14>C. Another stable isotope ^<15>N, of which natural abundance is only 0.366%, is usable, but high enrichment above 99.5 %, preferably 99.9 % is necessary. The scope of the present research project initiated in 2004 has two targets; one is to develop the process for high enrichment of ^<15>N by ion exchange and the other is to develop inherently safe reprocessing which is appropriate for nitride fuels discharged from fast breeder reactors. Concerning ^<15>N enrichment, super high enrichment of 99.99% ^<14>N was attained at the first step. Then, enrichment of ^<15>N from natural level of 0.366 % was studied and 21.5 % ^<15>N was obtained. Based on these results, high enrichment of 99.91 % ^<15>N was successfully attained by ion exchange chromatography. For the development of inherently safe reprocessing, we obtained fundamental information on the innovative reprocessing system of ion exchange resin and HCI solutions. In the present work, our attention was directed to three major aspects, (1) recovery of platinum group elements, (2) recovery of technetium and (3) separation of minor actinides, americium and curium, from lanthanide elements. It was found that a set of tertiary pyridine resin and HC1 acid system has excellent property as total element separation system. Platinum group elements, Ru, Rh and Pd, and Tc are adsorbed at low HC1 solutions, and Tc is recovered with 6 M HC1 solution. At high concentration of HCl, americium and curium is adsorbed and separated from lanthanides.
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