Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 21

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

The Uranium waste fluid processing examination by liquid and liquid extraction method using the emulsion flow method

Kanda, Nobuhiro; Daiten, Masaki; Endo, Yuji; Yoshida, Hideaki; Mita, Yutaka; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki

JAEA-Technology 2015-007, 43 Pages, 2015/03

JAEA-Technology-2015-007.pdf:5.33MB

The centrifuge which has the subtlety information concerning the nuclear nonproliferation used for uranium enrichment technical development exists in the uranium enrichment facilities of Ningyo-toge Environmental Engineering Center, Japan Atomic Energy Agency. This centrifugal is performing separation processing of the radioactive material adhering to the surface of parts by wet decontamination of ultrasonic cleaning by dilute sulfuric acid and water, etc. By removing the uranium contained in waste fluid, generated sludge reduces activity concentration. And the possibility of reduction of sludge processing is examined. For this reason, from the 2007 fiscal year, Nuclear Science and Engineering Directorate and cooperation are aimed at, and development of the extraction separation technology of the "uranium" by the emulsion flow method is furthered. The test equipment using the developed emulsion flow method was tested. And dilute sulfuric acid and water were used for the examination as actual waste fluid. The result checked whether the various performances in Basic test carried out in Nuclear Science and Engineering Directorate would be obtained.

JAEA Reports

Detailed investigation on the environmental effects from the liquid effluent of JNC reprocessing plant (IV); (April, 1996$$sim$$March, 2000)

; Shinohara, Kunihiko; ; ; ; Isozaki, Tokuju; ; *

JNC TN8440 2000-003, 93 Pages, 2000/08

JNC-TN8440-2000-003.pdf:2.2MB

The investigation on the radioactivity concentration for gross beta, $$^{3}$$H and $$^{137}$$Cs in seawater collected around the discharge point had been performed in order to grasp the change of the activity level of the coastal seawater offshore the JNC Tokai Works from the low level liquid effluent of the reprocessing plant. After the investigation on the radioactivity in seawater during the hot examination, the detailed investigation on the environmental effects from the liquid effluent of JNC reprocessing plant has been performed since July 1978 on the basis of the request from Ibaraki prefecture as the full-scale operation of the reprocessing plant. Consequently, no increase of the radioactive concentration due to the discharged effluent has been observed. And also, as the result of the consideration to the investigation on the environmental effect from the liquid effluent throughout 22 years since 1978, no change of the radioactive concentration level in seawater was recognized.

JAEA Reports

Annual report on the environmental radiation monitoring around Tokai reprocessing plant FY 1999

; Shinohara, Kunihiko; ; ; ; Takeyasu, Masanori;

JNC TN8440 2000-007, 141 Pages, 2000/06

JNC-TN8440-2000-007.pdf:3.02MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during April 1999 to March 2000. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.

JAEA Reports

Radioactive waste treatment system in NUCEF

;

JAERI-Tech 99-045, 141 Pages, 1999/06

JAERI-Tech-99-045.pdf:5.38MB

no abstracts in English

JAEA Reports

None

*

PNC TJ1633 97-001, 40 Pages, 1997/03

PNC-TJ1633-97-001.pdf:2.0MB

no abstracts in English

JAEA Reports

None

PNC TN1700 93-008, 130 Pages, 1993/01

PNC-TN1700-93-008.pdf:2.46MB

no abstracts in English

JAEA Reports

None

PNC TN1700 93-002, 64 Pages, 1993/01

PNC-TN1700-93-002.pdf:0.91MB

no abstracts in English

JAEA Reports

Evaluation of bituminized product and plastics solidfication product

; ; ;

PNC TN8410 92-234, 26 Pages, 1992/09

PNC-TN8410-92-234.pdf:0.49MB

Low-level radioactive liquid wastes generated in the PNC Tokai Reprocessing Plant are solidified in bitumen, and solvent wastes generated in the Plant are solidified in plastics. They have been stored in the storage facility. To make sure that the stored wastes and their packages are in good condition, we evaluated the fundamental characteristics, eg, hardness, compressive strength, penetration, water content for solidified wastes, and observation thickess for packages. As a result, the characteristics of the stored wastes have not changed since they were solidified.

JAEA Reports

None

; ; ; *; *; *; *

PNC TN8420 92-020, 22 Pages, 1992/08

PNC-TN8420-92-020.pdf:0.73MB

None

JAEA Reports

None

Nakano, Tomoyuki;

PNC TN9420 92-008, 119 Pages, 1992/06

PNC-TN9420-92-008.pdf:3.71MB

None

JAEA Reports

None

Saito, Makoto; Yamada, Kazuo; Kitano, Mitsuaki; Kuroha, Mitsuhiko; Seimiya, Hiroshi

PNC TN8410 92-056, 43 Pages, 1992/03

PNC-TN8410-92-056.pdf:3.74MB

None

JAEA Reports

Removal of aerosol particles generated from glass melter for high level liquid waste vitrification

; ; Takahashi, Takeshi;

PNC TN8410 91-026, 27 Pages, 1991/02

PNC-TN8410-91-026.pdf:0.49MB

High level liquid waste originates from the reprocessing of spent fuel. The high level liquid waste is mixed and melted with borosilicate glass in the melter. During melting, radio-active aerosol is generated from the melter off-gas. Power Reactor and Nuclear Fuel Development Corporation is developing a vitrification process. The off-gas treatment system has been improved to reduce the release of radionuclides from the vitrification process to the atmosphere.

Journal Articles

Development of collective dose assessment codes for a spent nuclear fuel reprocessing plant in Japan

Togawa, Orihiko; Homma, Toshimitsu

Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management: RECOD91,Vol. 1, p.253 - 258, 1991/00

no abstracts in English

Journal Articles

Collective dose assessment methodology for a spent nuclear fuel reprocessing plant

Togawa, Orihiko; Homma, Toshimitsu

Proc. of the CSNI Specialist Meeting on Safety and Risk Assessment in Fuel Cycle Facilities, p.351 - 360, 1991/00

no abstracts in English

JAEA Reports

None

Seimiya, Hiroshi; Yamada, Kazuo; Kuroha, Mitsuhiko; Saito, Makoto; Tomikawa, Hirofumi; Saito, Toru*; Hagiya, Shinichi*

PNC TN8410 90-082, 90 Pages, 1990/09

PNC-TN8410-90-082.pdf:6.81MB

None

JAEA Reports

None

Saito, Makoto

PNC TN8410 90-059, 19 Pages, 1990/06

PNC-TN8410-90-059.pdf:0.78MB

None

JAEA Reports

None

Sasaki, Noriaki; Yusa, Yasuhisa

PNC TN8410 89-041, 88 Pages, 1989/06

PNC-TN8410-89-041.pdf:2.11MB

None

JAEA Reports

None

Tsunoda, Naomi; Sasaki, Noriaki; Nagaki, Hiroshi

PNC TN841 80-22, 104 Pages, 1980/04

PNC-TN841-80-22.pdf:6.4MB

no abstracts in English

JAEA Reports

None

Segawa, Takeshi*; Hoshino, Tadaya*; *; *; ; *; *

PNC TN841 74-14, 48 Pages, 1974/06

PNC-TN841-74-14.pdf:1.39MB

no abstracts in English

Oral presentation

Development of steam reforming system for treatment of difficult-to-treat organic liquid wastes, 2; Applicability of a repair method for refractory materials treating inside of main reactor in steam reforming system

Kijima, Jun; Koyama, Hayato; Owada, Mitsuhiro; Shibata, Atsuhiro

no journal, , 

Japan Atomic Energy Agency (JAEA) has been developing a steam reforming system and equipment for the treatment of difficult-to-treat organic liquid wastes. The main reactor, which is a main component of the treatment system, has a refractory material on the inner surface. Cracks and flakes were observed on the surface of the refractory material due to age-related deterioration. Therefore, we repaired the deteriorated refractory material surfaces using two types of repair materials and conducted combustion tests on simulated samples to evaluate each repair material. After the combustion test, we concluded that the repair of the main reactor using the repair materials was possible, since there were no cracks or flakes of repair materials.

21 (Records 1-20 displayed on this page)