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Nakamura, Hideo
Nihon Genshiryoku Gakkai-Shi ATOMO
, 61(4), p.270 - 272, 2019/04
no abstracts in English
Fujita, Mitsutane*; Xu, Y.*; Kaji, Yoshiyuki; Tsukada, Takashi; Mashiko, Shinichi*; Onose, Shoji*
RIST News, (38), p.3 - 14, 2004/11
The distributed materials database system named "Data-Free-Way(DFW)" has been developed with the collaboration of three organizations: the National Institute for Materials Science, the Japan Atomic Energy Research Institute, and the Japan Nuclear Cycle Development Institute over the Internet since 1990. At present, the development of a distributed knowledge based system, in which knowledge extracted from DFW is expressed, is planned with the collaboration of three organizations as we add data into DFW and make DFW open for the public use. Network technique and presentation and acquisition technique of the information developed rapidly and these techniques brought about a revolution in the society and our daily life changed. This paper describe the present status of DFW and future direction of the material databases with the transition of information technology.
Owada, Hitoshi*; Mihara, Morihiro; Iriya, Keishiro*; *
JNC TN8400 99-057, 43 Pages, 2000/03
Cementitious materials are considered as candidate materials for the geological disposal of high-level radioactive waste and TRU waste. As the pH and the Ca content of leachate from the cementitious materials are high, the host rock and the buffer-material would be degraded by the leachate in the long-term. Therefore, transport properties and parameters such as solubilities and distribution coefficients of radionuclides would be changed and affect the performance of the repository. In order to dissolve this "High pH plobrem", the use of a low alkalinity cement is considered for the disposal. In this study, we summarized the necessity of the low alkalinity cement, and developed the approach of the low alkalinization of cement. And, the following were carried out in this study : A leaching test of cement paste, a fluid test of the mortar and a installation test of the concrete to the trial structure. From the leaching test using the cement paste, we confirmed that we were able to obtain the low alkalinity cement (HFSC) by addition of pozzolanic materials such as silica-fume and flyash. From the result of the fluid test of the mortar, we chose the cement for the practicability evaluation. The practicability of low alkalinity concrete was evaluated by installation test to the trial structure.As a result of these examinations, we proved that the pH value of the leachate from the cementitious material was reduced by adding SF and FA to Portland cement. Simultaneously, SF and FA had to be added in order to obtain the good workability. In addition, workability and mechanical strength of the cement which SF and FA were added are almost equivalent to the ordinary Portland cement. The results shows that the HFSC has high practicability.
*; *; *; *
JNC TJ9440 2000-007, 43 Pages, 2000/03
JNC-TJ9440-2000-007.pdf:1.73MB
Planning of the plutonium utihzation in the Light water thermal reactor has been investigated to evaluate scenario for FBR development. Plans for MOX fuel utilization in the ABWR including Ooma plant are studied, and information of high burnup fuels for a future BWR is summarized based on public documents. Nuclear compositions of the present burnup fuel (45,000MWd/t) and a high burnup fue (60,000MWd/t) have been evaluated using an open code: SRAC. Results of the study are follows; (1)Surveying the status of MOX fuel utilization. The status of MOX and UO
fuel utilization in the present BWR and future BWR have been summarized based on public documents. (2)Evaluation of spent MOX and UO fuel composition. Nuclear compositions of spent MOX and UO fuels at 45,000MWd/t and 60,000MWd/t burnup have been evaluated and summarized for recycle scenarios by FBR.
Takeuchi, Suehiro
Kasokuki No Genjo To Shorai; Genshiryoku Sentan Gijutsu, 5, (6), p.46 - 53, 1998/06
no abstracts in English
Bottcher, J. T.
PNC TN9440 97-011, 215 Pages, 1997/06
J.H.Bottcher started his intemational Fellow position at PNC on March 25, 1996.During his 15 months in PNC he worked in the Irradiation Section of the Experimental Reactor Division. There he worked on conceptual design reviews and related the US irradiations methodology to the members. His work extended to other Divisions at OEC and Tokai Works, mainly related to fuel development and irradiation performance. In these efforts he published two papers, wrote a desip review document, and presented six lectures on irradiated fuels and materials. In addition he participated in coordinating a new four year PNC/DOE collaborative program on irradiated steels characterization.
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
PNC TN1410 93-012, 24 Pages, 1992/09
The "First progress report of research and development ongeological disposal of high level radioactive waste",H3 in short,is intended for the Japanese authorities. In accordance with the "Overall program for high level radioactive waste management" set forth by atomic energy commission, H3 is designed to clarify the current status of the research and development work performed by power reactor and nuclear fuel development corporation (PNC) up to the year 1991. H3 presents the updated knowledge on Japan's geological environment, the technology of geological disposal and the performance assessment of the multi-barrier system as a basis for further research and development with the objective of confirming scientific and technical feasibility of the geological disposal concept in Japan. The contents of H3 issummarized in this document.
Genshiryoku Kogyo, 39(1), p.67 - 72, 1992/00
no abstracts in English
Tominaga, Hiroshi
Nihon Genshiryoku Gakkai-Shi, 32(7), p.670 - 673, 1990/07
no abstracts in English
mu
alpha, 1990(WINTER), p.95 - 97, 1990/00
no abstracts in English
