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Notoya, Shin; Sasao, Eiji; Ota, Kunio; Shimizu, Kazuhiko
JAEA-Conf 2010-004, 119 Pages, 2010/11
JAEA-Conf-2010-004.pdf:16.59MB
In March 2010, a prototype of "next generation" knowledge management system (KMS) and a status report (CoolRep H22) synthesizing the R&D results were made publicly available at the conclusion of R&D for the first Midterm Plan (October 2005 to March 2010). This could further reinforce the technical knowledge base and thus enable the geological disposal project and associated safety regulations to be continuously supported. The conference on "Development of JAEA Knowledge Management System, 2010" was held on 16th June 2010 in Tokyo, with main aims of introducing KMS and CoolRep H22 to broader stakeholders, promoting their understanding and having input from them for further improvement of KMS. This report compiles presentation materials and comments to KMS and CoolRep H22 from participants.
Notoya, Shin; Ota, Kunio; Shimizu, Kazuhiko
JAEA-Conf 2009-005, 58 Pages, 2010/02
Geological Isolation Research and Development Directorate has now been developing a "next generation" knowledge management system (KMS) that would continuously support the disposal project and associated safety regulations. Work has been also ongoing on synthesizing the results of R&D for the first midterm plan in the style of "next generation" scientific reporting "CoolRep" which is strongly linked with KMS. In March 2010, a prototype of KMS and a status report (CoolRep H22) will be made publicly available. It is thus of much significance to promote stakeholder's understanding of KMS and CoolRep and have input from them at this timing in order to efficaciously proceed with the future work. To this end, the conference on "Progress in Development of JAEA Knowledge Management System" was held on 1st July 2009 in Tokyo. This report compiles presentation materials and comments/input to KMS and CoolRep from the stakeholders.
Seo, Toshihiro; Sasao, Eiji; Notoya, Shin; Shimizu, Kazuhiko
Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10
JAEA has promoted research and development of HLW disposal technology to contribute to both implementation and safety regulation. This R&D covers the geological environment, repository engineering and performance assessment. At two underground laboratories (Mizunami and Horonobe), surface-based investigations have been completed, and the excavation of shafts and drifts is underway. A complementary study of natural disruptive phenomena, such as volcanism and faulting, has also been conducted. In the ENTRY and QUALITY research facilities, the development of engineering technologies with associated advanced models and databases for quantification of the long-term evolution of the near-field has been carried out. To integrate these R&D activities and manage the huge amount of data that they produce, JAEA has initiated a novel project to develop an advanced knowledge management system which will provide a technical knowledge base for supporting both implementers and regulators.
Toshiyasu, Suguro,; Notoya, Shin; Nishikawa, Yoshiaki*; Nakamura, Ryosuke*; Shibutani, Tomoki; Kuroha, Mitsuhiko; Kamei, Gento
JNC TN8430 2004-004, 27 Pages, 2005/01
JNC-TN8430-2004-004.pdf:1.03MB
In terms of safety assessment of TRU waste disposal, data on plutonium sorption on cementitious materials have been obtained by means of a static batch-type experiment. Because the repository condition will be reducing and be affected by considerable amount of nitrate, the authors carried out the experiments using ordinary portland cement (OPC) under the reducing (Na
SO
as added as reductant) and anoxic condition (O 
1ppm) and solution of 0 to 0.5 M NaNO
. Other experimental conditions are : liquid/solid (L/S) ratios ; 100 and 1000 mL g
, Initially aaded plutonium; 2.84
10
M, Temperature; 25
5
C and Reaction times; 7, 14 and 28 days. The experimental results suggest that distribution coefficient (
) ranges 50 to 1000 mL g in case of L/S=100mL g. Similarly the ranges, 100 to 10000 mL g at L/S=1000mL g. These values tend to increase with lapsing reaction time. On the basis of these results, we recommend 50mL g as a conservative value of plutonium on OPC in a TRU waste repository condition.
Kato, Tomoko; Fujishima, Atsushi; Ueno, Kenichi; ; Notoya, Shin; Sonobe, Hitoshi
JNC TN8450 2001-003, 205 Pages, 2001/01
JNC-TN8450-2001-003.pdf:77.1MB
We have compiled and refined the information materials to explain ENTRY (Engineering Scale Test and Research Facility) and QUALITY (Quantitative Assessment Radionuclide Migration Experimental Facility). These include information materials to show activities for research and development of radioactive waste disposal in Tokai Works such as panels of experimental equipments. This work was carried out by a working group in Waste Isolation Research Division, Waste Management and Fuel Cycle Research Center; Tokai Works in 1998
2000. We have developed database for above information materials including typical experimental equipments of ENTRY and QUALITY. In the future, it can be easily refind in case of reconstruction of the experimental equipments. This report presents the database including the experimental equipments and several pamphlet.
*; Shibata, Masahiro; Yoshida, Yasushi*; ; Notoya, Shin; Yui, Mikazu
JNC TN8400 99-071, 140 Pages, 1999/11
The solubilities and speciation dataset for the selected safety-relevant elements in the second progress reports (H12), except for a soluble element (Cs), in the porewater compositions of the compacted bentonite, which are used in the H12 assessments, are provided in this report. The solubilities and speciation were basically determined by thermodynamic calculation using thermodynamic database of the radioactive elements, assuming chemical equilibrium with simple solubility limiting solid phase. For some elements, the solubilities were determined by comparing experimental solubility data, considering the conservatism of the solubility dataset. For radium, the solubility was determined based on simple co-precipitation model with alkaline earth elements. The variation of solubilities and speciation were also examined and discussed, considering the uncertainty of porewater chemistry, assumption of solubility limiting solid phase, and thermodynamic data.
Notoya, Shin; Shibutani, Tomoki; Okazaki, M.*; Inui, Shinichi*; Kuroha, Mitsuhiko; Yui, Mikazu
JAERI-Conf 99-004, p.643 - 653, 1999/03
None
; ; Kuroha, Mitsuhiko; Yui, Mikazu; *; *
JAERI-Conf 99-004, p.643 - 653, 1999/03
None
Takeuchi, Shinji; Notoya, Shin; Ota, Kunio; Shimizu, Kazuhiko
no journal, ,
no abstracts in English
