Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Aoki, Isao; ; Haga, Tetsuya; ; Sudo, Katsuo; Tsunashima, Yasumichi;
JNC TN8420 2000-005, 42 Pages, 2000/04
JNC-TN8420-2000-005.pdf:2.09MB
On August 1999, the Director of Tokai Work proposed an activity regarding recycling and reuse of general waste generated from Tokai Works. The activity was initiated by the Waste Management and Fuel Cycle Research Center, and is now being in progress through out the Tokai Works. In the course of this activity, Plutonium Fuel Center had settled the Working Group and the issues related to the waste reduction have been examined. This report collects the problems that became obvious through the survey of existing segregation method, treatment process, and the amount of the waste generation, and accounts for the concrete methodology for the recycling and reuse of general waste. In order to reduce waste, it is necessary to aware of the facing issues and adopt the countermeasures proposed in this report whenever possible. The activity will then leads us to reduce waste generation, which in turn will enable us to make 100 % waste recycling possible.
; Nishikawa, Yoshiaki*; Kagawa, Akio;
JNC TN8400 2000-017, 30 Pages, 2000/03
JNC-TN8400-2000-017.pdf:1.97MB
The influence of the cement additives on the distribution coefficients of americium-241 to the Ca-bentonite was confirmed. The adsorption experiment of americium-241 to Ca-bentonite with cement additives was performed by the batch method, as a part of the influence evaluation of the organic in the research of TRU waste disposal. As a result, the distribution coefficient of americium-241 to the Ca-bentonite was over 1.2E+3m
/kg in the condition of the absence of cement additives. In the case of low concentration (0.3g/kg) of the naphthalenesulfonic acid type cement additives, the distribution coefficient was 5.2E+2mkg. And, in the case of high concentration (30g/kg) of the same cement additives, the distribution coefficients was 2.0E-1m/kg. On the other hand in the case of flow concentration (0.5g/kg) of the polycarboxylic acid type cement additives, the distribution coefficients was over 1.3E+3m/kg. And, in the case of high concentration (50g/kg) of the same cement additives, the distribution coefficient was 1.8E-1m/kg. Here, selected cement additives concentrations were based on a standard concentration of 10g/kg when the ratio of water:cement is about one. From these results, the distribution coefficient of americium-241 to the Ca-bentonite decreases according cement additive concentration. The distribution coefficients were similar on different kinds of cement additives. The cement additives concentration influences the distribution coefficient. The distribution coefficient was small in the case of high concentration of the cement additives. That is, it is thought that the cement additives have small influences on the distribution coefficient of americium-241 to the Ca-bentonite in the case of low concentration, though the cement additives have influences on the distribution coefficient of americium-241 to the Ca-bentonite in the case of high concentration.
; Koide, Kaoru*; *; Yoshida, Eiichi; *; ; Fujita, Tomoo
PNC TN1410 97-038, 307 Pages, 1996/04
no abstracts in English
; Kobayashi, Hiroaki; Masaki, Toshio; *; Kawamura, Kazuhiro; ;
PNC TN8440 94-028, 173 Pages, 1994/06
None
Yamato, Aiji; Sasaki, Noriaki; ; Miyahara, Kaname
PNC TN1100 94-002, 85 Pages, 1993/11
Nuclear energy is the second largest source of electric power in the United States. Tdate, nuclear power plants produced over twenty percent of the nation's electricity. Aof August 1991, there were 112 nuclear power reactors in the United States, and two mo were being built. By the year 2000, approximately 40,000 metric tons of nuclear wasteill be in temporary storage at reactor sites throughout the coutry. That amount is twi the amount that currently exists. In order to handle such waste, as well as the addedolume to be produced after the year 2000, the U. S. Department of Energt (DOE) is in t process of developing the waste management system that was authorized by the U. S Coness in 1987. The authorized system is illustrated in Figure 1. To summarize, spent nucar fuel from commercial power reactors will be accepted by the DOE at the reactor siteand transported to a monitored retrievable storage (MRS) facility for temporary storagand preparation for permanent disposal in a gelogic rep
Miyahara, Kenji; Yamamura, Osamu; Takahashi, Keizo; Sugiyama, Toshihide; ; Ikeda, Hisashi
PNC TN8440 91-022, 42 Pages, 1991/04
This paper is compiled as a record of oral presentation by O.YAMAMURA at RECOD' 91 in April 15. 1991 in Sendai Japan with more than 600 attendance. It contains a proceeding, a manuscript of oral presentation and a manuscript of viewgraphs. The abstract of presentation is as belows. Since the start of construction of the Tokai Reprocessing Plant (TRP) in 1971, large efforts were taken by the Power Reactor and Nuclear Fuel Development Corporation (PNC) and various organizations to root the LWR fuel reprocessing technology in Japan. These efforts produced many achievements around the TRP, and now the future plan for the TRP is being studied.