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Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger; Project overview

Yamano, Hidemasa; Kurisaka, Kenichi; Takano, Kazuya; Kikuchi, Shin; Kondo, Toshiki; Umeda, Ryota; Shirakura, Shota*

Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2023/09

This project studies investigation on safety design guideline and risk assessment technology for sodium-cooled fast reactor with the molten-salt heat storage system, development of evaluation method for heat transferring performance between sodium and molten-salt and improvement of the performance, and evaluation of chemical reaction characteristic between sodium and molten-salt and improvement of its safety. The project overview is presented in this report.

Journal Articles

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger

Yamano, Hidemasa; Kurisaka, Kenichi; Takano, Kazuya; Kikuchi, Shin; Kondo, Toshiki; Umeda, Ryota; Shirakura, Shota*; Hayashi, Masaaki*

Proceedings of 8th International Conference on New Energy and Future Energy Systems (NEFES 2023) (Internet), p.27 - 34, 2023/00

 Times Cited Count:0 Percentile:0.05(Green & Sustainable Science & Technology)

This project studies investigation on safety design guideline and risk assessment technology for sodium-cooled fast reactor with the molten-salt heat storage system, development of evaluation method for heat transferring performance between sodium and molten-salt and improvement of the performance, and evaluation of chemical reaction characteristic between sodium and molten-salt and improvement of its safety. The project overview is presented in this report.

Journal Articles

Extraction properties of trivalent rare earth ions from nitric acid using a triamide-amine extractant

Uchino, Seiko*; Narita, Hirokazu*; Kita, Keisuke*; Suzuki, Hideya*; Matsumura, Tatsuro; Naganawa, Hirochika*; Sakaguchi, Koichi*; Oto, Keisuke*

Solvent Extraction Research and Development, Japan, 30(1), p.39 - 46, 2023/00

The extraction of trivalent rare earth ions (RE$$^{3+}$$) from HNO$$_{3}$$ solution using a triamide amine, tris(N,N-di-2-ethylhexyl-ethylamide)amine (DEHTAA), was conducted, and the extraction mechanism was estimated from extraction behavior of HNO$$_{3}$$ and RE$$^{3+}$$ and the relationship between atomic number and extraction percentages (E%) for RE$$^{3+}$$. A DEHTAA molecule dominantly formed a DEHTAA HNO$$_{3}$$ at 1.0 M HNO$$_{3}$$ and a DEHTAA(HNO$$_{3}$$)$$_{2}$$ at 6.0 M HNO$$_{3}$$ in the acid-equilibrated organic phase. This would provide the unique dependence of E% for the light RE$$^{3+}$$ on the HNO$$_{3}$$ concentration, in which the E% value had a minimum and maximum at $$sim$$0.5 M and $$sim$$2 M HNO$$_{3}$$, respectively. The results of the slope analyses for the distribution ratios for RE$$^{3+}$$ suggested that the dominant RE$$^{3+}$$ complex was RE(NO$$_{3}$$)$$_{3}$$DEHTAA(DEHTAA HNO$$_{3}$$) at 1.0 M HNO$$_{3}$$. The E% for RE$$^{3+}$$ decreased from La$$^{3+}$$ to Lu$$^{3+}$$ at 1.0 M HNO$$_{3}$$; on the other hand, those increased from La$$^{3+}$$ to Nd$$^{3+}$$ at 0.25 M and from La$$^{3+}$$ to Sm$$^{3+}$$ and 6.0 M HNO$$_{3}$$.

JAEA Reports

None

*

JNC TJ6420 2000-005, 109 Pages, 2000/07

JNC-TJ6420-2000-005.pdf:3.16MB

no abstracts in English

Journal Articles

Extraction chromatography in the DHDECMP-HNO$$_{3}$$ system, II; Characteristics of the DHDECMP/XAD-4 resin on separation of trivalent actinide elements

Kimura, Takaumi; Akatsu, Jokun

Journal of Radioanalytical and Nuclear Chemistry, 149(1), p.25 - 34, 1991/00

 Times Cited Count:10 Percentile:72.11(Chemistry, Analytical)

no abstracts in English

Journal Articles

Extraction chromatography in the DHDECMP-HNO$$_{3}$$ system, I; Extraction behaviour of Ce(III) and Am(III) with the DHDECMP/XAD-4 resin

Kimura, Takaumi; Akatsu, Jokun

Journal of Radioanalytical and Nuclear Chemistry, 149(1), p.13 - 23, 1991/00

 Times Cited Count:17 Percentile:84.03(Chemistry, Analytical)

no abstracts in English

Journal Articles

Extraction chromatography in the TBP-HNO$$_{3}$$ system, II; Characteristics of the TBP/XAD-4 resin on separation of actinide elements

Kimura, Takaumi

Journal of Radioanalytical and Nuclear Chemistry, 141(2), p.307 - 316, 1990/00

 Times Cited Count:12 Percentile:74.09(Chemistry, Analytical)

no abstracts in English

Journal Articles

Extraction chromatography in the TBP-HNO$$_{3}$$ system, I; Extraction behaviour of Th(IV) and U(VI) with the TBP/XAD-4 resin

Kimura, Takaumi

Journal of Radioanalytical and Nuclear Chemistry, 141(2), p.295 - 306, 1990/00

 Times Cited Count:18 Percentile:83.14(Chemistry, Analytical)

no abstracts in English

Journal Articles

Separation of zirconium from fission products in silica gel-nitric acid systems

;

Analytica Chimica Acta, 84(2), p.347 - 353, 1976/02

 Times Cited Count:7

no abstracts in English

Journal Articles

Separation of antimony-125 in fission products

; *;

Journal of Nuclear Science and Technology, 11(12), p.571 - 574, 1974/12

 Times Cited Count:7

no abstracts in English

Oral presentation

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger, 1; Project overview

Yamano, Hidemasa; Kurisaka, Kenichi; Takano, Kazuya; Kikuchi, Shin; Kondo, Toshiki; Umeda, Ryota; Hayashi, Masaaki*

no journal, , 

This project studies investigation on safety design guideline and risk assessment technology for sodium-cooled fast reactor with the molten-salt heat storage system, development of evaluation method for heat transferring performance between sodium and molten-salt and improvement of the performance, and evaluation of chemical reaction characteristic between sodium and molten-salt and improvement of its safety. The project overview is presented in this report.

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