Current status of the AMS facility at the Tono Geoscience Center of the Japan Atomic Energy Agency

Kokubu, Yoko; Nishizawa, Akimitsu*; Suzuki, Mototaka*; Owaki, Yoshio*; Nishio, Tomohiro*; Matsubara, Akihiro; Saito, Tatsuo; Ishimaru, Tsuneari; Umeda, Koji; Hanaki, Tatsumi

Nuclear Instruments and Methods in Physics Research B, 294, p.43 - 45, 2013/01

https://doi.org/10.1016/j.nimb.2012.01.050

The Tono Geoscience center of JAEA installed the JAEA-AMS-TONO system at 1997. Since 1998, the system has routinely used for C-AMS. Recently, about 800 samples/y have been measured mainly for studies of neotectonics and hydrogeology in relation to research of geosphere stability for long-term Isolation of high-level radioactive waste. Under the common-use facility program, the system has also been used by researchers of universities and other institutes. In addition, Be-AMS has been developed for geochronological study. A gas ionisation detector was exchanged. As the detector has a gas absorber cell which has larger volume than the previous one, it is possible to remove B efficiently. Test measurement by using several standard samples supplied from University of California, Berkeley was performed. Ratios of Be/Be were comparable to the certified values, indicating that our system has sufficient ability to be useful to Be-AMS.

Extraction and separation of uranium from simulated uranium-containing liquid wastes of Ningyo-toge environmental engineering center

Mitamura, Hisayoshi; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki; Hanzawa, Yukiko; Shimojo, Kojiro; Matsubara, Tatsuo; Mita, Yutaka; Taki, Tomihiro; Murata, Masato

JAEA-Research 2008-113, 27 Pages, 2009/03

JAEA-Research-2008-113.pdf:31.84MB

An effective mass processing equipment using solvent extraction method, named "emulsion flow extractor," is the most promising apparatus for removal and recovery of uranium from liquid waste originated from decontamination of uranium-contaminated fluoride waste in the uranium conversion test facility and of used gas centrifuges in the uranium enrichment facility at Ningyo-toge environmental engineering center. Prior to application of the emulsion flow extractor for actual uranium-containing liquid waste, properties of some phosphorous extractants for extraction and separation of uranium and constituents from simulated liquid wastes were examined through batch tests. These preliminary tests revealed that D2EHPA would be a promising candidate for extractant used for treatment of the actual uranium-containing liquid wastes, and that the extractants with a surfactant like AOT would not be useful.

Buckling fracture of PVC ventilation duct by the in-line monitor sampling

Matsubara, Tatsuo; Endo, Yuji; Yamanaka, Toshihiro; Kuramoto, Takao; Daiten, Masaki; Sugitsue, Noritake

no journal, , 

The hard vinyl chloride ventilation duct of the local ventilation equipment for used centrifuge decommissioning system had fractured despite the ventilation stopping. As a result of investigation of the causes, it was found that negative pressure in the isolated duct with the damper valve exceeded buckling limit because the air sampling of air-sniffer was not stopped. For experimental proof of this, we investigated of attained negative pressure, analyzed buckling stress and confirmed that hard vinyl chloride ventilation duct was fractured quickly by negative pressure buckling with the mock-up examination device.