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JAEA Reports

Emulsion and Accumulation at Aqueous/Organic Interface of Mlxer-Settlers

Gonda, Kozo; Yasu, Shozo*;

PNC TN841 84-52, 14 Pages, 1984/09

PNC-TN841-84-52.pdf:0.25MB

The emulsion Which results from Di-n-butylphosphoric scid (HDBP) and zirconium (HDBZr emulsion) was studied on the formation ratio to the emulsion of nonsoluble fissioproduct residues (nonsoluble residues emulsion) in the condecontamination cyclewithoutsolvent washing. HDBP-Zr emulsion was found three times of nonsoluble residues emsion by one week's operation of the codecontamination cycle with the spent nuclear fl burnt to 28,000 MWd/MTU and cooled 1,000 days. In this codecontamination cycle, 1 HDBP was salted out at the aqueous/organic interface as HDBP-Zr emulsion, and10% HDBP dissolved in the recycling solvent stream as HDBP-U complex. It was found that HP-Zr emulsion accelerates the volume growth of nonsoluble residues emulsion by the elsifying effect.

Journal Articles

Characteristics and behavior of emulsion at nuclear fuel reprocessing

Gonda, Kozo

Nuclear Technology, 57(2), p.192 - 202, 1982/05

 Times Cited Count:25 Percentile:89.36(Nuclear Science & Technology)

JAEA Reports

None

Nemoto, Takeshi; Gonda, Kozo;

PNC TN842 82-01, 114 Pages, 1982/03

PNC-TN842-82-01.pdf:4.75MB

None

JAEA Reports

Calculation code PULCO for purex process in pulsed column

Gonda, Kozo; Matsuda, Teruo*

PNC TN841 82-19, 363 Pages, 1982/03

PNC-TN841-82-19.pdf:8.55MB

no abstracts in English

JAEA Reports

None

Gonda, Kozo; ; Fukuda, Shoji*

PNC TN841 80-71, 167 Pages, 1980/09

PNC-TN841-80-71.pdf:3.02MB

no abstracts in English

JAEA Reports

Application of electro-reduction to Purex process

Gonda, Kozo; Matsuda, Teruo*

PNC TN841 80-65, 71 Pages, 1980/09

PNC-TN841-80-65.pdf:1.57MB

no abstracts in English

JAEA Reports

None

; ; ; Gonda, Kozo

PNC TN841 80-13, 37 Pages, 1980/03

PNC-TN841-80-13.pdf:2.7MB

no abstracts in English

JAEA Reports

None

Shibahara, Tetsuro; Gonda, Kozo

PNC TN841 80-03, 35 Pages, 1980/01

PNC-TN841-80-03.pdf:0.85MB

no abstracts in English

JAEA Reports

None

Gonda, Kozo; ; ;

PNC TN841 80-01, 128 Pages, 1980/01

PNC-TN841-80-01.pdf:2.95MB

no abstracts in English

JAEA Reports

Text book of dose calculation for operators

; Gonda, Kozo

PNC TN852 79-13, 126 Pages, 1979/07

PNC-TN852-79-13.pdf:4.09MB

None

JAEA Reports

None

Gonda, Kozo;

PNC TN841 79-26, 240 Pages, 1979/02

PNC-TN841-79-26.pdf:5.11MB

no abstracts in English

JAEA Reports

None

Gonda, Kozo; Nemoto, Takeshi; Shibahara, Tetsuro

PNC TN841 79-06, 27 Pages, 1979/02

PNC-TN841-79-06.pdf:0.5MB

no abstracts in English

JAEA Reports

None

Gonda, Kozo; Nemoto, Takeshi; Yasu, Shozo*;

PNC TN841 79-05, 32 Pages, 1979/02

PNC-TN841-79-05.pdf:0.85MB

no abstracts in English

JAEA Reports

None

Gonda, Kozo; Nemoto, Takeshi; Yasu, Shozo*;

PNC TN841 78-60, 29 Pages, 1978/11

PNC-TN841-78-60.pdf:0.84MB

no abstracts in English

JAEA Reports

Text book of purex process for operators

Gonda, Kozo

PNC TN852 77-08, 175 Pages, 1977/11

PNC-TN852-77-08.pdf:6.24MB

None

JAEA Reports

None

Gonda, Kozo; Fukuda, Shoji*

PNC TN841 77-60, 204 Pages, 1977/09

PNC-TN841-77-60.pdf:5.13MB

no abstracts in English

JAEA Reports

Extraction Processes on Reprocessing of Fast Reactor Fuel in a Purex Plant Constructed for Light Water Reactor Fuel

Gonda, Kozo; Yasu, Shozo*; Kawashima, Nobuyoshi*; Hoshino, Tadaya*; Tanaka, Chuzaburo*

PNC TN841 72-14, 28 Pages, 1972/05

PNC-TN841-72-14.pdf:0.59MB

The extraction processes on repro-cessing Japanese Experimental Fast Reactor (JEFR, named as JOYO) fuelhave been studied with an unirrad-iated uranium and plutonium,suppo-sing that the JEFR fuel will betreated with no modification of thefacilities and the operation condi-tions except the solvent employedand the dilution of the fuel in the PNC Purex plant under constructionfor the exclusive use of lightwater reactor fuels. The applicability of the extractionfacilities in PNC plant to theextraction of JEFR fuel was verified,concerning the recoveries of uraniumand plutonium in the co-decontamina-tion cycle,even in the case that thesolvent was changed to 10% TBP from 30% TBP employed in a light waterreactor fuel reprocessing・Also,theValidity of 30% TBP system on thepartition cycle of uranium and plut-onium was confirmed with regard tostripping plutonium.

JAEA Reports

None

Hoshino, Tadaya*; Gonda, Kozo; Yasu, Shozo*; Kawashima, Nobuyoshi*

PNC TN841 71-22, 30 Pages, 1971/08

PNC-TN841-71-22.pdf:0.79MB

no abstracts in English

19 (Records 1-19 displayed on this page)
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