None

Nemoto, Takeshi; Okada, Takashi; ; Ouchi, Jin; Kondo, Isao

PNC TN8410 92-119, 45 Pages, 1992/06

PNC-TN8410-92-119.pdf:0.8MB

None

Determination of tritium concentration in fuel reprocessing liquid waste by vacuum freeze distillation

Journal of Nuclear Science and Technology, 13(8), p.442 - 448, 1976/08

https://doi.org/10.3327/jnst.13.442

no abstracts in English

Decontamination of alkali chloride baths containing nuclear material by precipitation and distillation techniques

Ibe, Junya*; Aso, Megumi*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*

no journal, , 

Since waste salt generated from pyro-reprocessing test which contains uranium can easily capture moisture from the air and corrode equipment and piping material, further treatment technology for decontamination and waste stabilization is required. The aim of this study is to develop a simple separation method for decontamination of salts. In the first step, oxides are added as oxygen donor in the melts to uranium. In the next step, melt bath components are evaporated by a vacuum distillation. LiCl-KCl eutectic and NaCl-2CsCl salts were used as melt baths, lithium oxide was used as a precipitant, and cerium chloride was used as uranium surrogate for testing the precipitation process. By characterization with XRD and EXAFS, it is considered that oxychloride was formed. By pulverization of the salt and increase the distillation time, distillation ratio of the salt from the sample was achieved up to 90%.

Decontamination of alkali chloride baths containing nuclear material by precipitation and distillation techniques; Distillation experiment

Ibe, Junya*; Mitani, Mao*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*

no journal, , 

no abstracts in English

Decontamination of alkali chloride baths containing uranium by precipitation and distillation techniques

Ibe, Junya*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*

no journal, , 

no abstracts in English