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Kanda, Nobuhiro; Daiten, Masaki; Endo, Yuji; Yoshida, Hideaki; Mita, Yutaka; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki
JAEA-Technology 2015-007, 43 Pages, 2015/03
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.
; Shinohara, Kunihiko; ; ; ; Isozaki, Tokuju; ; *
JNC TN8440 2000-003, 93 Pages, 2000/08
The investigation on the radioactivity concentration for gross beta, H and 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.
; Shinohara, Kunihiko; ; ; ; Takeyasu, Masanori;
JNC TN8440 2000-007, 141 Pages, 2000/06
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.
;
JAERI-Tech 99-045, 141 Pages, 1999/06
no abstracts in English
; ; ;
PNC TN8410 92-234, 26 Pages, 1992/09
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.
Saito, Makoto; Yamada, Kazuo; Kitano, Mitsuaki; Kuroha, Mitsuhiko; Seimiya, Hiroshi
PNC TN8410 92-056, 43 Pages, 1992/03
None
; ; Takahashi, Takeshi;
PNC TN8410 91-026, 27 Pages, 1991/02
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.
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
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
Seimiya, Hiroshi; Yamada, Kazuo; Kuroha, Mitsuhiko; Saito, Makoto; Tomikawa, Hirofumi; Saito, Toru*; Hagiya, Shinichi*
PNC TN8410 90-082, 90 Pages, 1990/09
None
Yoshimori, Michiro; *;
Hoken Butsuri, 24, p.271 - 275, 1989/00
no abstracts in English
Tsunoda, Naomi; Sasaki, Noriaki; Nagaki, Hiroshi
PNC TN841 80-22, 104 Pages, 1980/04
no abstracts in English
Segawa, Takeshi*; Hoshino, Tadaya*; *; *; ; *; *
PNC TN841 74-14, 48 Pages, 1974/06
no abstracts in English
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.