Investigation and analytical results of bituminized products in drums at filling room

Shibata, Atsuhiro; ; ; Kitajima, Takafumi;

JNC TN8410 99-029, 192 Pages, 1999/09

JNC-TN8410-99-029.pdf:54.79MB

This report describes the results of investigation of the bituminized products in drums, liquid waste in the receiving tank V21 and the bituminized mixture in the extruder. The investigation of the products in drums showed most of the unburned products filled after 28 B had abnormality, such as hardened surfaces, caves and porous brittle products. The particle sizes of the salt fixed in bituminized products depended neither on batch number nor on feed rate. It indicates the filling of the salt particle caused by the decreased feed rate did not occur. The measured concentrations of metals and anions in the bituminized products showed no abnormality. The catalytic content was not recognized in the products. The infrared absorption spectra obtained with the bituminized products show the oxidation at the incident occrred without oxygen. There was no organic phase on the surface of liquid waste in V21. Chemical analysis and thermal analysis on the precipitate in V21 showed no abnormality. Concentration of sodium nitrate/nitrite in the mixture collected from the extruder was lower than normal products. These results show no chemical activation of the bituminized products. It can be concluded that the chemical characteristics of the products had little abnormality even around the incident.

Investigation of operating condition; The report for investigation of bituminization demonstration facility incident(4/7)

; ; Kurosawa, A.; Hayashi, Naomi; Kobayashi, Kentaro; Kitajima, Takafumi; Sato, Yoshihiko

PNC TN8410 98-047, 278 Pages, 1998/02

PNC-TN8410-98-047.pdf:19.5MB

The fire and explosion incident occurred at the Bituminization Demonstration Facility of the Tokai Reprocessing Plant on march 11th, 1997. For investigation of Bituminization Demonstration Facility Incident and prevention relapse, Investigation Group for Bituminization Demonstration Facility incident was set up. It has been investigated the situation at the time of incident was occurred. The result of investigated was presented for Science and Technology Agency. This report is arranged the result of investigated the situation for investigation and prevention relapse.

Engineering scale demonstration test of centrifugal contactor system, 5; Comparison of solvent washing performance between salt-free and alkali reagents by internal reflux type

Takeuchi, Masayuki; Onose, Tsutomu*; Fujisaku, Kazuhiko*; Arai, Yoichi; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Renovation of CPF (Chemical Processing Facility) for development of advanced fast reactor fuel cycle system

Aose, Shinichi; Ogasawara, Koji; Nomura, Kazunori; Miyachi, Shigehiko; Ichige, Yoshiaki; Shinozaki, Tadahiro; Ouchi, Shinichi; Kitajima, Takafumi

no journal, , 

no abstracts in English

Fundamental test of crystallization process; Evaluation of U solubility in solution of irradiated fuel

Kaji, Naoya; Nakahara, Masaumi; Nakamura, Kazuhito; Shibata, Atsuhiro; Tomita, Yutaka; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

Solubility obtained from the latest crystallization tests using irradiated fuel and the tests implemented before using U or Pu/U are compared with the data showed by Hart. Based on the result, availability of the data to estimate crystallization ratio is considered.

Uranium, plutonium and neptunium co-recovery by single cycle extraction process (Neptunium extraction behaviour on high concentration acid condition)

Miyachi, Shigehiko; Nakahara, Masaumi; Sano, Yuichi; Nomura, Kazunori; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

The hot experiments on solvent extraction conducted in the Chemical Processing Facility (CPF) has demonstrated that the oxidation of Np in the feed solution from Np(V) to Np(VI) by making the acidity higher than conventional condition is effective in the co-recovery of U, Pu and Np so far. Furthermore, it was confirmed that Np was quantitatively recovered with U and Pu by applying of highly acidic scrubbing solution under the conventional condition of the acidity of the feed solution. The main results obtained are presented in this report.

Fundamental test of crystallization process; Experience on behavior of FPs in crystallization process by using irradiated MOX fuel

Kaji, Naoya; Nakamura, Kazuhito; Nomura, Kazunori; Shibata, Atsuhiro; Yano, Kimihiko; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

For the purpose of obtaining DFs of the short-life FPs by analysis in the hot experiment, fundamental test of crystallization process was carried out using Fast Experimental Reactor "JOYO" irradiated fuel. In this experiment, DFs of nuclides analyzed by analysis except Cs (Such as Ru-106, Ce-144, Pr-144) and Pu were evaluated to be about 100. It was suggested that there is the condition in which Pu-Cs double salt does not be formed, although DF of Cs had been very low in the past experiments because of forming Pu-Cs double salt.

Experimental study on fuel shearing with irradiated fast reactor fuel at CPF

Ouchi, Shinichi; Shibata, Atsuhiro; Nomura, Kazunori; Miyachi, Shigehiko; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English