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JAEA Reports

Technical report on the development of finance and contract information system Ver.4

Kimura, Hideo; Hikasa, Naoki*; Kugenuma, Yuji*; Doi, Toshiharu*; Kikuchi, Yoshitaka*

JAEA-Technology 2019-004, 25 Pages, 2019/05

JAEA-Technology-2019-004.pdf:3.02MB

JAEA has developed the "Financial and contract information system" for effective and efficient accomplishment of the mission-critical tasks. Because the development of the next system was necessary with the end in the support time limit of the current system, we carried out the development of the next system in 2018. While the addition of the electronic approval function or the adoption of the latest package software largely performed a functional enhancement until now by applying distributed systems construction technique based on the separation procurement that we devised progressively, in development, we extremely realized procurement with the low cost.

Journal Articles

Development of Nondestructive Measurement Techniques for Uranium-contaminated Waste in Containers

Oki, Koichi; Aoyama, Yasuhiro; Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Sagawa, Hiroshi*; Hideo, Doi,*; Endo, Yasumi*

Waste Management 2005 Proceeding, CD-ROM, 8p., 8 Pages, 2005/03

We developed as a new technique to remove the influence of distance between radionuclides and detectors. We named the technique "the Facing Couple Method (FCM)". Partcality inspection which uses uranium source was parformed.Furthermore, the application possibility to a system was confirmed.

Journal Articles

Development of Technique for Measuring Uranium Quantity within Containers Using the Passive Gamma Method

Oki, Koichi; Aoyama, Yasuhiro; Sukegawa, Yasuhiro*; Suzuki, Satoshi*; Sagawa, Hiroshi*; Hideo, Doi,*; Endo, Yasumi*

Saikuru Kiko Giho, (25), p.57 - 68, 2004/00

https://rdreview.jaea.go.jp/gihou/pdf3/n25-07.pdf

The system which measures and evaluates the quantity of uranium in the uranium contaminated waste in a large-sized container by NDA technology was manufactured.Practicality inspection which uses an uranium source was performed. Furthermore, the application possibility to a system was confirmed.

JAEA Reports

Study on the nuclide behavior in the engineered barrier for TRU waste (V)

Yanagisawa, Ichiro*; Katsurai, Kiyomichi*; Mukai, Satoru*; *

JNC TJ8400 2000-028, 224 Pages, 2000/02

JNC-TJ8400-2000-028.pdf:4.06MB

In this study, in-diffusion experiment was conducted under reducing condition to measure apparent diffusion coefficients and distribution coefficients of Uranium and Neptunium for bentonite materials as engineered barrier. The summary of this study is as follows: (1)Apparent diffusion coefficients of U and Np under reducing condition were one or two orders magnitude lower than those of the results obtained in the previous studies. From this result, the valence of U and Np was estimated to be +4 charge during diffusion experiment. (2)Distribution coefficients of U and Np for the system of equilibriated water with bentonite at density of 1.6 g/cm $^{3}$ were a little lower than those for the other synthetic groundwater system. (3)Distribution coefficients of Cs and Sr decreased as ion strength of pore water in bentonite increased. Distribution coefficient of Sr increased for alternation of bentonite. (4)Distribution coefficients of Ni, Sn, Zr and Nb were little difference for any type of bentonite or synthetic groundwater. (5)Distribution coefficients or Am for Na-type of bentonite was higher than that of Ca-type of bentonite. But the difference of distribution coefficients for any synthetic groundwater was small. (6)Data base of apparent diffusion coefficients and distribution coefficients was renewed.