Investigation of chemical substances affect the fluidity of paste on cement solidification

Taniguchi, Takumi; Matsumoto, Saori; Hiraki, Yoshihisa; Sato, Junya; Fujita, Hideki*; Kaneda, Yoshihisa*; Kuroki, Ryoichiro; Osugi, Takeshi

JAEA-Review 2024-059, 20 Pages, 2025/03

JAEA-Review-2024-059.pdf:1.0MB

The basic performance required for solidifying waste into cement, such as fluidity before curing and strength after curing, is expected to be affected by the chemical effects of substances and components contained in the waste. The fluidity before curing and the strength properties after curing are greatly influenced by the curing speed of the cement. We investigated existing knowledge with a focus on chemical substances that affect the curing speed of cement. In this report, chemical substances that affect fluidity are broadly classified into inorganic substances such as (1) anion species, (2) metal elements such as heavy metals, (3) inorganic compounds as cement admixtures, and (4) organic compounds as cement admixtures. Based on the investigation, we actually added chemicals and measured the setting time. As a result, it was found that there are multiple mechanisms contributing to accelerated hardening. We investigated chemical substances that inhibit the curing reaction of cement, and were able to compile information to consider ingredients that are contraindicated in cement curing.

Development of waste management system, 1; Concept construction of the system

Kuroki, Ryoichiro; Ito, Fuminori*; Nakata, Hisakazu; Yamamoto, Shuji; Takahashi, Kuniaki

JAEA-Technology 2009-016, 124 Pages, 2009/06

JAEA-Technology-2009-016.pdf:3.8MB

The concept of "Waste Management System" which manages all the waste data from generation to disposal in Japan Atomic Energy Agency (JAEA) was studied. At first, development policy was defined on investigation results of the present state and problem of waste management in JAEA, and target information supplied by "Waste Management System" were extracted. Then over 400 data items to be managed in this system, system configuration and specific functions were shown as system concept. The waste data managed on this system are classified into two categories; for quality assurance of waste packages and for optimization study of waste conditioning and disposal and information service. This system consists of analytical part (i.e. program) and management part (i.e. database) for each data, then all these parts are constructed on network.

Proposal of a Nuclear Cycle Research and Development Plan in Tokai Works -The Roadmap from LWR Cycle to FBR Cycle-

Nakamura, Hirofumi; Abe, Tomiyuki; Kashimura, Takao; Nagai, Toshihisa; Maeda, Seiichiro; Yamaguchi, T.; Kuroki, Ryoichiro

JNC TN8440 2003-016, 39 Pages, 2003/07

JNC-TN8440-2003-016.pdf:0.79MB

The Generation-II Project Task Force Team has investigated a research and development plan on a future nuclear fuel cycle in Tokai works for about three months from December 19,2002. First we have discussed about the present condition of Japanese nuclear fuel cycle and have recognized it as the following. *The relation of the technology between the LWR-cycle and the FBR-cycle is not clear. *MOX Fuel Use in Light Water Reactors is important to establish technology of the FBR fuel cycle. *Radioactive waste disposal issue is urgent. Next we have proposed the three basic policies on R&D plan of nuclear fuel cycle in consideration of the F.S. on FBR-cycle. *Establishment and advancement of "the tough nuclear fuel cycle". *Early establishment of the FBR cycle technology to be able to supply energy stably for long-term. *Establishment of the radioactive waste treatment and disposal technology, and optimization of nuclear fuel cycle technology from the viewpoint of radioactive waste.And we have proposed the Japanese technical holder system to integrate all LWR and FBR cycle technology.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 2; Investigation of approach for selecting solidification techniques applied to contaminated water management waste

Furukawa, Shizue*; Koyama, Tadafumi*; Kikuchi, Michio*; Otsuka, Taku*; Yamamoto, Takeshi*; Imaizumi, Ken*; Osugi, Takeshi; Nakazawa, Osamu; Kuroki, Ryoichiro

no journal, , 

In order to evaluate the application to the solidification of the water treatment secondary waste generated from Fukushima Daiichi Nuclear Power Station, research concerning the approach of applicability evaluation was conducted for solidification technology of practical scale.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 5; Gamma-ray irradiation test on solidified body of cement and Alkali Activated Material

Taniguchi, Takumi; Imaizumi, Ken*; Namiki, Masahiro*; Osugi, Takeshi; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*

no journal, , 

It is important to understand fundamental solidification characteristics of contaminated water management waste at Fukushima Daiichi Nuclear Power Station. The Solidified bodies are fabricated with cementitious material and Alkali Activated Material, and are irradiated with Gamma-ray.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 4; Evaluation of dissolution behavior on solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Shibata, Masahito*; Kuranaga, Mebae*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kato, Jun; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

Solidified cement and alkali activated materials was made, and used for dissolution test to obtain basic data of solidification on the waste caused by the contaminated water treatment at Fukushima Daiichi Nuclear Power Station.

Environmental measures in the atomic industry of Japan (including the waste treatment and conditioning technology)

Kuroki, Ryoichiro

no journal, , 

(1) Environmental measures in the atomic industry of Japan (eliminattion of radioactive materials and toxic substances, effluent management, etc), (2) Summary of treatment and disposal of radioactive waste, (3) Development of waste treatment technologies, etc.

Introduction of research and development regarding treatment technology for TEPCO's Fukushima Daiichi NPS accident waste

Kato, Jun; Taniguchi, Takumi; Osugi, Takeshi; Nakazawa, Osamu; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Contaminated water treatment secondary wastes have diversity and have property without processing achievement so far. Tasks for applicability evaluation of these wastes were extracted concerning solidification technologies with applied achievement for radioactive waste processing by FY2017. This report introduces research and development for solving the extracted tasks.

Physical properties test for solidification strength and long-term stability of K-based alkali-activated materials

Kakuda, Ayaka; Osone, Osamu*; Hiraki, Yoshihisa; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kudo, Isamu*; Elakneswaran, Y.*; Sato, Tsutomu*

no journal, , 

no abstracts in English

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 10; Characteristic evaluation of carbonate slurry-containing solidified body formed by cement or alkali activated material

Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kawato, Takaya*; Kaneda, Yoshihisa*; Shibata, Masahito*; Haga, Kazuko*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

In order to obtain data to be used in the evaluation of the applicability of low temperature processing to carbonate slurry generated by contaminated water treatment at Fukushima Daiichi Nuclear Power Station, the basic properties of the solidified cement and alkali activated material blended simulated carbonated slurry were evaluated. An overview of the study and some of the results obtained are reported here.