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Journal Articles

XAFS analysis of ruthenium in simulated iron phosphate radioactive waste glass

Okamoto, Yoshihiro; Kobayashi, Hidekazu; Shiwaku, Hideaki; Sasage, Kenichi; Hatakeyama, Kiyoshi*; Nagai, Takayuki

Journal of Non-Crystalline Solids, 551, p.120393_1 - 120393_8, 2021/01

 Times Cited Count:0 Percentile:0.02(Materials Science, Ceramics)

The chemical state of ruthenium in simulated iron phosphate radioactive waste glass was investigated by conventional X-ray absorption fine structure (XAFS) and imaging XAFS analyses. The EXAFS analysis suggested that ruthenium was contained as glass phase when content of the waste components was less than 10wt.% in 30 mol%Fe$$_{2}$$O$$_{3}$$-P$$_{2}$$O$$_{5}$$ base glass. In other samples, crystalline RuO$$_{2}$$ was predominant. According to the imaging XAFS analysis, RuO$$_{2}$$ particles in all samples had length smaller than 50$$mu$$m. Aggregations of RuO$$_{2}$$, which are found in nuclear waste borosilicate glass, were not seen in any of the iron phosphate glass samples.

JAEA Reports

XAFS measurement of simulated waste glass samples (Joint research)

Nagai, Takayuki; Sasage, Kenichi; Okamoto, Yoshihiro; Shiwaku, Hideaki; Yamagishi, Hirona*; Ota, Toshiaki*; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Takahashi, Tomoe*; et al.

JAEA-Research 2019-003, 94 Pages, 2019/09

JAEA-Research-2019-003.pdf:7.92MB

The local structures of glass-forming elements and waste elements would change by the chemical composition of waste glass including those elements. In this study, simulated waste glass samples were prepared from borosilicate glass frit including phosphorus (P) or vanadium (V), and we investigated local structures of boron, sodium, and waste elements in these P glass and V glass samples by using synchrotron XAFS measurements in soft and hard X ray region.

JAEA Reports

XAFS measurement of simulated waste glass samples prepared from borosilicate glass frit including phosphorus pentaoxide (Joint research)

Nagai, Takayuki; Kobayashi, Hidekazu; Shimamura, Keisuke; Oyama, Koichi; Sasage, Kenichi; Okamoto, Yoshihiro; Shiwaku, Hideaki; Yamanaka, Keisuke*; Ota, Toshiaki*

JAEA-Research 2018-005, 72 Pages, 2018/09

JAEA-Research-2018-005.pdf:28.2MB

Addition of radioactive waste to a borosilicate glass frit affects the local structures of glass-forming elements and waste elements in a waste glass produced in a vitrification process. In this study, simulated waste glass samples were prepared from borosilicate glass frit including phosphorus pentaoxide, and we investigated local structures of sodium (Na), boron (B), and waste elements in these glass samples by using synchrotron XAFS measurements in soft and hard X ray region.

JAEA Reports

XAFS measurement of simulated waste borosilicate glass samples (Joint research)

Nagai, Takayuki; Kobayashi, Hidekazu; Sasage, Kenichi; Ayame, Yasuo; Okamoto, Yoshihiro; Shiwaku, Hideaki; Yamanaka, Keisuke*; Ota, Toshiaki*

JAEA-Research 2017-005, 54 Pages, 2017/06

JAEA-Research-2017-005.pdf:16.17MB

Addition of radioactive waste to a borosilicate frit affects the local structures of boron (B) and waste elements in a waste glass. Synchrotron XAFS measurement was applied to investigate the local structural changes by using simulated waste borosilicate glass samples. Following results were obtained by the B K-edge XAFS analysis. It was confirmed that B K-edge XAFS analysis enables us to discriminate sp$$^{2}$$ type boron (BO$$_{3}$$) from sp$$^{3}$$ type boron (BO$$_{4}$$). Addition of waste elements to a glass frit increases the percentage of BO$$_{3}$$ and decreases that of BO$$_{4}$$. By decreasing the SiO$$_{2}$$/Al$$_{2}$$O$$_{3}$$ ratio or increasing the (SiO$$_{2}$$+B$$_{2}$$O$$_{3}$$)/Al$$_{2}$$O$$_{3}$$ ratio in the glass composition, the BO$$_{3}$$ percentage increases and the BO$$_{4}$$ percentage decreases. Addition of P$$_{2}$$O$$_{5}$$ decreases the BO$$_{3}$$ percentage and increases the BO$$_{4}$$ percentage. Following results were obtained from XAFS measurement of the waste elements. Cerium (Ce) valence is more reduced with the increase of the B$$_{2}$$O$$_{3}$$ content. Addition of P$$_{2}$$O$$_{5}$$ has a tendency to reduce the Ce valence and to enhance deposition of Zr oxide. Deposition of ruthenium compounds separated from glass phase can not be improved by changing the B$$_{2}$$O$$_{3}$$ content. This study was performed as a part of the project, "Improvement of vitrification process of high-level radioactive liquid wastes" on the foundation business of the Agency for Natural Resources and Energy.

Journal Articles

Chemical behavior of platinum group compounds in the vitrification process condition

Nagai, Takayuki; Akiyama, Daisuke*; Sato, Nobuaki*; Sasage, Kenichi

Busshitsu, Debaisu Ryoiki Kyodo Kenkyu Kyoten Kenkyu Seika Hokokusho (Heisei-28-Nendo) (CD-ROM), 1 Pages, 2017/03

no abstracts in English

JAEA Reports

XAFS measurement of simulated waste glass samples (Borosilicate glass including vanadium)

Nagai, Takayuki; Kobayashi, Hidekazu; Sasage, Kenichi; Ayame, Yasuo; Okamoto, Yoshihiro; Shiwaku, Hideaki; Matsuura, Haruaki*; Uchiyama, Takafumi*; Okada, Yukiko*; Nezu, Atsushi*; et al.

JAEA-Research 2016-015, 52 Pages, 2016/11

JAEA-Research-2016-015.pdf:37.48MB

The local structure of waste elements in simulated waste glasses including V was estimated by using synchrotron XAFS measurement in this study. The results are as follows. (1) V has a high possibility which exists in the glass phase in the case of frit, and V can regard both samples as stable 4 coordination structure. (2) Zn, Ce, Nd, Zr, and Mo exist in the glass phase, and the difference is admitted by the percentage of Ce(III) and Ce(IV) by the composition. (3) Ru is separated from the glass phase as RuO$$_{2}$$ crystalline, both of metal and oxide exist in Rh, and Pd is separated out as metal. (4) It was confirmed that the regularity of the local structure of Zr and Mo in the molten glasses retreats as a result of the XAFS measurement at high temperature. (5) The XAFS measurement of molten glasses were performed at 1200$$^{circ}$$C, so it would be possible to acquire excellent data by improving the shapes of the sample cell.

Journal Articles

Investigation of ruthenium compounds in the vitrification process condition

Nagai, Takayuki; Sato, Nobuaki*; Sasage, Kenichi

Busshitsu, Debaisu Ryoiki Kyodo Kenkyu Kyoten Kenkyu Seika Hokokusho (Heisei-27-Nendo) (CD-ROM), 2 Pages, 2016/03

no abstracts in English

JAEA Reports

None

*; *; *; Sasage, Kenichi

JNC TY8400 2003-004, 41 Pages, 2003/03

JNC-TY8400-2003-004.PDF:0.83MB

no abstracts in English

JAEA Reports

Measurement of glass transition temperature of waste glass by differential thermal analysis (DTA); Research report on solidification of high-level liquid waste

Ouchi, Jin; ; ; *; ; Sasage, Kenichi; Odakura, Makoto

PNC TN8410 97-044, 53 Pages, 1997/03

PNC-TN8410-97-044.pdf:1.57MB

The glass transition temperature of simulated waste glass was measured by DTA installed in CPF (Chemical Processing Facility) and HTS (High Level Waste Technology Section). This measurement was intended to confirm the agreement between hot and cold data as a part of characterization of high level waste glass. Glass transition temperature is an index of the temperature to keep thermal stability of high-level waste glass. Since devitrification deteriorates characteristics of waste glass above glass transition temperature, it is necessary to measure glass transition temperature and keep glass temperature below glass transition temperature. The conventional method to determine glass transition temperature is the measurement of thermal expansion, but DTA is adopted for radioactive sample because of easier preparation. We obtained following results by measuring glass transition temperature of simulated waste glasses after calibration with standard specimen : (1)The average glass transition temperature of TVF waste glass (P0798) measured by DTA in HTS and CPF was 494$$^{circ}$$C (standard deviation 3 $$sigma$$: 8.2$$^{circ}$$C) and 495$$^{circ}$$C (3$$sigma$$: 1.8$$^{circ}$$C), respectively. The difference between two analyzer was 1$$^{circ}$$C. It shows the good agreement between hot and cold DTA data. (2)Glass transition temperature of P0798 measured by thermal expansion method was 495$$^{circ}$$C(3$$sigma$$: 8.1$$^{circ}$$C) and it agrees well with that measured by DTA. (3)The average glass transition temperature of simulated highly waste-loading glass (P1102) measured by DTA in HTS and CPF was 510.5 $$pm$$2.5$$^{circ}$$C.

Journal Articles

None

; ; ; Sasage, Kenichi; ; Ouchi, Jin

Donen Giho, (98), p.85 - 90, 1996/06

None

JAEA Reports

None

Sasage, Kenichi

PNC TN8510 95-002, 351 Pages, 1995/04

PNC-TN8510-95-002.pdf:21.8MB

None

JAEA Reports

None

Sasage, Kenichi; ; Ouchi, Jin

PNC TN8100 94-003, 337 Pages, 1994/02

PNC-TN8100-94-003.pdf:11.69MB

no abstracts in English

JAEA Reports

None

*; ; ; ; Sasage, Kenichi; ; Ouchi, Jin

PNC TN8100 94-002, 104 Pages, 1994/02

PNC-TN8100-94-002.pdf:3.08MB

no abstracts in English

Oral presentation

Feasibility study on volume reduction technology of HLLW vitrification

Kobayashi, Hidekazu; Sasage, Kenichi; Usui, Yasufumi; Ayame, Yasuo; Shiotsuki, Masao

no journal, , 

no abstracts in English

Oral presentation

Development of long-life vitrification melter, 7; Examination on the behavior of particulate in vitrified waste

Miyauchi, Atsushi; Morikawa, Yo; Sasage, Kenichi; Yamashita, Teruo; Shiotsuki, Masao

no journal, , 

no abstracts in English

Oral presentation

Development of long-life vitrification melter, 5; Characterization of vitrified waste

Sasage, Kenichi; Miyauchi, Atsushi; Morikawa, Yo; Yamashita, Teruo; Shiotsuki, Masao

no journal, , 

Viscosity and specific resistivity of simulated waste glass was measured to investigate characterization of waste glass processed by the long-life vitrification melter. The composition of the simulated waste glass was varied based on 8 cases of assumed spent fuel conditions and reprocessing flows including reprocessing of FBR fuel with minor actinides separation. The viscosity of the sample glasses was from 0.5 to 1.8 times that of waste glass with standard composition. The specific resistivity of the sample glasses was from 0.5 to 1.5 times that of standard waste glass.

Oral presentation

Development of long-life vitrification melter, 11; Influence of suspended particle on viscosity of molten glass

Sasage, Kenichi; Nakajima, Masayoshi; Yamashita, Teruo; Shiotsuki, Masao; Matsumoto, Shiro*

no journal, , 

no abstracts in English

Oral presentation

Applicability examination of solidification by borosilicate glass to the advanced fuel cycle system

Kano, Shigeru; Kobayashi, Hidekazu; Yamashita, Teruo; Sasage, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Storage and disposal of the high level waste from the advanced FBR fuel cycle

Nishihara, Kenji; Oigawa, Hiroyuki; Nakayama, Shinichi; Fujiwara, Takeshi; Kobayashi, Hidekazu; Kano, Shigeru; Sasage, Kenichi; Yamashita, Teruo; Ono, Kiyoshi; Shiotani, Hiroki

no journal, , 

The reduction of the storage facility and repository were evaluated for the cases with or without partitioning of Sr-Cs and transmutation of MA in the advanced FBR fuel cycle with the cost estimation for the storage facilities, transporting and repository. As the result, the transmutation of minor actinides is inevitable for the small repository because the heat generation by $$^{241}$$Am is considerable in FBR. The introduction of partitioning, transmutation and long-term storage enable the very compact layout in the repository like TRU wastes such as hulls and end-pieces of the fuel assembly. The cost for the storage and disposal in this case is much smaller than that in other cases, which mitigates the cost increase by the separation process and transmutor.

Oral presentation

Development of advanced vitrification melter, 16; Examination on the discharge of particulate in vitrified waste

Nakazaki, Katsutoshi; Morikawa, Yo; Yamashita, Teruo; Sasage, Kenichi; Nakajima, Masayoshi

no journal, , 

no abstracts in English

45 (Records 1-20 displayed on this page)