User's guide of cement solidification test for incinerated ash

Nakayama, Takuya; Kawato, Yoshimi; Osugi, Takeshi; Shimazaki, Takejiro; Hanada, Keiji; Suzuki, Shinji; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro

JAEA-Technology 2014-046, 56 Pages, 2015/03

JAEA-Technology-2014-046.pdf:7.61MB

The combustible and flame-retardant radioactive wastes generated as a result of the research activities in Japan Atomic Energy Agency (JAEA) are incinerating to reduce their volume. The incinerated ash is planned to be solidified using cement for disposal. Since the properties of ashes generated in each institute of JAEA are varied with the type of incinerator and the wastes to be incinerated, it is necessary to do fundamental solidification tests in each institute to decide operating conditions of the planning cement solidification facility. It is important to standardize evaluating methods of cement and solidified waste because some characters depend on measuring method. This user's guide have been prepared how to decide the cement solidifying conditions of ash to design the cement solidification facility in JAEA. Requirements on the regulations of solidified radioactive waste have been examined and seven technical criteria, e.g. compressive strength, fluidity, have been selected as characters to be evaluated. Some empirical notes about selection of cement, admixtures, procedure on making a test piece, evaluation of expanding, compressive strength, solubility have been described. The strategy of tests and tips for finding optimized solidification condition has been summarized. Finally the example of optimized conditions satisfied the requirements and some problems to be solved have been described.

Cause finding experiments and environmental analysis on the accident of the fire and explosion in TRP bituminization facility

Fujine, Sachio; Murata, Mikio; Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; Miyata, Teijiro*; Ida, Masaaki*; Watanabe, Makio; Uchiyama, Gunzo; Asakura, Toshihide; et al.

JAERI-Research 99-056, p.278 - 0, 1999/09

JAERI-Research-99-056.pdf:22.73MB

no abstracts in English

Study on long-term integrity assessment for engineered barriers; Overview of testing plan in under-ground research laboratory

Nakayama, Mariko*; Kobayashi, Masato*; Kawakubo, Masahiro*; Suzuki, Kei*; Eto, Jiro*; Nakayama, Masashi; Ono, Hirokazu; Asano, Hidekazu*

no journal, , 

no abstracts in English

Remote maintenance in Tokai Vitrification Facility, 1; Experience and demonstrations

Nakayama, Jiro; Sumi, Hirotaka; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji

no journal, , 

no abstracts in English

Evaluation of corrosion in the equipment containing high level radioactive liquid waste

Sumi, Hirotaka; Makigaki, Hikaru; Nakayama, Jiro; Niitsuma, Koichi; Kodaka, Akira

no journal, , 

no abstracts in English

Application to radioactive waste of ferrite waste liquid treatment method; Study of the stability of the product by micro-PIXE analysis method

Abe, Tomohisa; Shimazaki, Takejiro; Nakayama, Takuya; Osone, Osamu; Osugi, Takeshi; Nakazawa, Osamu; Yuri, Yosuke*; Yamada, Naoto*; Sato, Takahiro*

no journal, , 

no abstracts in English