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Journal Articles

Radiochemical research for the advancement of $$^{99}$$Mo/$$^{99m}$$Tc generator by (n,$$gamma$$) method

Fujita, Yoshitaka; Seki, Misaki; Namekawa, Yoji*; Nishikata, Kaori; Kimura, Akihiro; Shibata, Akira; Sayato, Natsuki; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.

KURNS Progress Report 2018, P. 155, 2019/08

no abstracts in English

Journal Articles

Separation of Ru(III), Rh(III) and Pd(II) from nitric acid solutions using ion-exchange resins bearing carboxylic betaine

Suzuki, Tomoya; Morita, Keisuke; Sasaki, Yuji; Matsumura, Tatsuro

Separation Science and Technology, 51(17), p.2815 - 2822, 2016/09

 Times Cited Count:2 Percentile:83.46(Chemistry, Multidisciplinary)

To understand the adsorption properties of styrene-divinylbenzene copolymer functionalized with ${it N,N,N}$-trimethylglycine, AMP03, the adsorption behaviors for platinoid ions (Ru(III), Rh(III), and Pd(II)) were examined. Furthermore, we performed adsorption experiments using sample solutions with adding triethylamine, thiourea, and ${it N,N,N}$-trimethylglycine. Based on the adsorption data obtained in this study, we performed chromatographic experiments. The results indicated that all platinoid ions in the feed solution completely adsorbed on AMP03, and almost 80% of the adsorbed platinoid ions were recovered. These results show that AMP03 has the potential to recover Ru(III), Rh(III), and Pd(II) from high-level liquid waste.

Journal Articles

Development of $$^{99}$$Mo/$$^{99m}$$Tc generator for the $$^{99}$$Mo/$$^{99m}$$Tc domestic production

Fukumitsu, Nobuyoshi*; Tsuchiya, Kunihiko; Ariga, Katsuhiko*; Yamauchi, Yusuke*

Isotope News, (742), p.20 - 24, 2016/02

no abstracts in English

Journal Articles

Experiments of continuous gas separation for D$$_{2}$$/He mixed gas under room temperature

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya

Shinku, 46(3), p.154 - 157, 2003/03

no abstracts in English

Journal Articles

Preliminary experiments on the separation of perfluorocompounds by continuous circulation gas chromatography

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya; Futatsuki, Takashi*; Tajima, Yoshinori*

Shinku, 46(1), p.44 - 48, 2003/01

no abstracts in English

Journal Articles

Study on gaseous effluent treatment for dissolution step of spent nuclear fuel reprocessing

Mineo, Hideaki; Iizuka, Masaru*; Fujisaki, Susumu; Hotoku, Shinobu; Asakura, Toshihide; Uchiyama, Gunzo

Proceeding of International Waste Management Symposium 2002 (WM '02) (CD-ROM), 9 Pages, 2002/00

no abstracts in English

Journal Articles

Preliminary experiments for continuous separation of H$$_{2}$$/He mixture gas

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya; Inohara, Takashi*

Shinku, 44(7), p.667 - 670, 2001/07

no abstracts in English

JAEA Reports

A Study on the reprocessing of spent FBR-fuel by ion exchange

*; Arai, Tsuyoshi*; *

JNC-TJ9400 2000-002, 80 Pages, 2000/02

JNC-TJ9400-2000-002.pdf:4.67MB

In order to develop an economically efficient wet separation process other than solvent extraction for reprocessing spent FBR-fuel (MOX fuel), we have investigated the possibility of an advanced ion exchange process. Based on the fundamental research results, we proposed an advanced ion exchange process considering the characteristics of FBR-fuel cycle. The separation system consists of a main separation process using a novel anion exchanger which has a rapid kinetics and two extraction chromatography processes for minor actinides isolation using novel impregnation adsorbents with high selectivity. The chemical flow sheet, mass balance chart, list of main equipment and installation layout of each equipment were estimated and designed for the process in a reprocessing plant with the capacity of 200 tHM/y FBR-fuel. The process was pfeliminarny evalualed from the aspects of economy performance, recovery of potentially useable resources, minimization of environmental risk and proliferation-resistance by comparing with the advanced PUREX process. Furthermore, the subjects which are important for the practical application of the process are also listed.

JAEA Reports

The Study on degradation of engineered barrier in radioactive waste repositories effect of nitrate and leaching solutions

Iriya, Keishiro*; *; Fujita, Hideki*; Kubo, Hiroshi*

JNC-TJ8400 2000-034, 212 Pages, 2000/02

JNC-TJ8400-2000-034.pdf:7.91MB

Cementious materials and highly compacted bentnite are expectable candidates as materials of TRU waste repositories. It was pointed out that Bentonite might be changed to Zeolite and surrounding rock might be altered by high alkalinity water flow, since cement hydrate leached to pore water of cement and it was changed to alkaline. Transportation of radio-nuclides might be accelerated by organic materials, such as super plasticizer, and nitlate which is contained in nuclear wastes. It was concluded by previous studies that rock and bentonite is stable in alkaline water which pH is less than 10.5. The new type of low alkalinity cement with high silica fume and fly ash content which could keep pH below 11.0 was developed and its performance has been assessed. However since Zeolitation and ilitation were reported upon deterioration of bentonite bated in certain condition, it should be assessed by long term experiment. Since Capacity of keeping integrity of bentonite hasn't been directly checked by experiments upon the developed new type of low alkalinity cement it should be done. Although amount of leaching organic was quantitatively and experimentally assessed at an early age, effect of changing of amount and shape hasn't assessed in leaching of radio nuclides. Although it is pointed out that deterioration of cementitious materials isn't accelerated by condensed nitrate solution at early period after closure, it is considered that it might be accelerated corresponding to chemical composition in case of decrement of concentration of nitrate. In this study, deterioration of materials will be assessed in detail in order to feed back the results to assessment of transportation of radio nuclides. Long term deterioration of bentonite by leaching water of cement will be experimentally assessed, and deteriorating test of bentonite will be carried out by leaching water of low alkalinity cement. Amount of organic and component of it will be measured. Furthermore ...

JAEA Reports

The Study on degradation of engineered barrier in ratioactive waste repositories effect of nitrate and leaching solutions

Iriya, Keishiro*; *; Kubo, Hiroshi*; Fujita, Hideki*

JNC-TJ8400 2000-033, 95 Pages, 2000/02

JNC-TJ8400-2000-033.pdf:11.11MB

Cementious materials and highly compacted bentnite are expectable candidates as materials of TRU waste repositories. It was pointed out that Bentonite might be changed to Zeolite and surrounding rock might be altered by high alkalinity water flow, since cement hydrate leached to pore water of cement and it was changed to alkaline. Transportation of radio-nuclides might be accelerated by organic materials, such as super plasticizer, and nitrate which is contained in nuclear wastes. It was concluded by previous studies that rock and bentonite is stable in alkaline water which pH is less than 10.5. The new type of low alkalinity cement with high silica fume and fly ash content which could keep pH below 11.0 was developed and its performance has been assessed. However since Zeolitation and ilitation were reported upon deterioration of bentonite bated in certain condition, it should be assessed by long term experiment. Since Capacity of keeping integrity of bentonite hasn't been directly checked by experiments upon the developed new type of low alkalinity cement it should be done. Although amount of leaching organic was quantitatively and experimentally assessed at an early age, effect of changing of amount and shape hasn't assessed in leaching of radio nuclides. Although it is pointed out that deterioration of cementitious materials isn't accelerated by condensed nitrate solution at early period after closure, it is considered that it might be accelerated corresponding to chemical composition in case of decrement of concentration of nitrate. In this study, deterioration of materials will be assessed in detail in order to feed back the results to assessment of transportation of radio nuclides. Long term deterioration of bentonite by leaching water of cement will be experimentally assessed, and deteriorating test of bentonite will be carried out by leaching water of low alkalinity cement. Amount of organic and component of it will be measured. Furthermore ...

Journal Articles

$$alpha$$ bearing waste treatment by electrochemical oxidation technique

Sugikawa, Susumu; Umeda, Miki

Proceedings of 2nd International Conference on Safewaste 2000, Vol.1, p.357 - 364, 2000/00

no abstracts in English

JAEA Reports

Tests on decisive proof for the incinerating and melting facility using the in-can type high frequency induction heating

; ; ; ;

JNC-TN9410 2000-002, 149 Pages, 1999/12

JNC-TN9410-2000-002.pdf:23.51MB

LEDF (Large Equipment Dismantling Facility) is the solid waste processing technology development facility that carries out high-volume reduction and low dosage processing. The high-volume reduction processing of the high dose $$alpha$$-waste configured with combustible waste, pvc & rubber, spent ion exchange resin, and noncombustible waste have been planned the incinerating and melting facility using the in-can type high frequency induction heating in LEDF. This test is intended to clarify the design data. It was confirmed that the incinerating and melting performance, molten solid properties and exhaust gas processing performance with pilot testing equipment and bench scale equipment. The result of this test are as follows. (1)Processing speed is 6.7kg/h for the combustible waste, 13.0kg/h for the ion exchange resin, and 30.0kg/h for the noncombustible waste. For above optimum processing conditions are as follows. (a)Operating temperature is 1000$$^{circ}$$C for the combustible waste, 1300$$^{circ}$$C for the ion exchange resin, 1500$$^{circ}$$C for the noncombustible waste. (b)Air flow is 90Nm$$^{3}$$/h. Air temperature is 300$$^{circ}$$C. Air velocity is 20m/s. (2)Incineration time per day is 5h. Warm-up time and incineration time from the stop of waste charging is 0.5h. Melting time per day is 5h inconsideration of heating hold time of incinerated ash and melting of quartz. Warm-up time is 0.5h. (3)The system decontamination factor in Co, Cs and Ce with pilot testing equipment is 10$$^{5}$$ or more. (4)Design data of the iron doped silica gel judged to be have a applicability as RuO$$_{4}$$ gas absorber is as follows. (a)Its diameter distribute in the range of 0.8-1.7mm. (b)To have a decontamination factor of 10$$^{3}$$ can achieve for retention time of 3 seconds and its life time is about 1 year. (5)In terms of the distribution of the nuclear species in molten solid is evenly distributed. It was also confirmed that the distribution of main elements in ceramic layer is ...

JAEA Reports

None

*; *; *

PNC-TJ6357 98-002, 43 Pages, 1998/02

PNC-TJ6357-98-002.pdf:1.09MB

None

JAEA Reports

None

Sugihara, Yoichiro*; Mukai, Katsuyuki*; Nunomiya, Ichiro*

PNC-TJ6357 97-001, 40 Pages, 1997/03

PNC-TJ6357-97-001.pdf:1.52MB

None

Journal Articles

Development of an integrated transuranic waste management system for a large research facility:NUCEF

Mineo, Hideaki; ; Takeshita, Isao; Nishizawa, Ichio; Sugikawa, Susumu; *

Nuclear Technology, 117(3), p.329 - 339, 1997/03

 Times Cited Count:1 Percentile:84.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of a highly efficient $$^{99m}$$Tc generator using a new adsorbent

Tanase, Masakazu; *; *

Isotope News, 0(509), p.6 - 9, 1996/10

no abstracts in English

Journal Articles

Synthesis of new adsorbents for Mo as an RI generator

*; *; *; *; *; Tanase, Masakazu;

Nippon Kagakkai-Shi, 0(10), p.888 - 894, 1996/00

no abstracts in English

JAEA Reports

None

Numata, Koji; ; Nemoto, Takeshi;

PNC-TN8430 93-001, 37 Pages, 1993/04

PNC-TN8430-93-001.pdf:0.34MB

None

JAEA Reports

None

Matsumoto, Shiro*

PNC-TJ1609 93-002, 14 Pages, 1993/03

PNC-TJ1609-93-002.pdf:0.25MB

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ1564 93-002, 23 Pages, 1993/02

PNC-TJ1564-93-002.pdf:0.53MB

None

42 (Records 1-20 displayed on this page)