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Watari, Shingo
JNC TJ8410 99-008, 41 Pages, 1999/12
On understanding the radionuclide transport in Natural Barrier in radioactive waste isolation research, the macroscopic dispersion in heterogeneous permeability field in the underground rock is regarded as an important process. Therefore, Japan Nuclear Cycle Development Institute (JNC) developed the MACRO experiment with an artificial heterogeneous permeability field and has been conducted lots of tracer experiments. To estimate the effect of characteristics of field on the macroscopic dispersion using data from those tracer experiments, the evaluation of dispersion coefficient is required. In this report, the macroscopic dispersion coefficients were evaluated for the results of the tracer experiments using the MACRO facility with a single well. The coefficients for the experiments of 18 cases were evaluated by the fitting of analytical solution to the breakthrough curve measured in the Well. In the evaluations, the correction of data measured in the experiments and of the accuracy in the evaluation were considered. The conclusions are as follows. (1)The macroscopic dispersion coefficients for 18 cases were evaluated using Least Square Method by fitting the analytical evaluation to the result of experiment. Consequently, the coefficients for 7 cases were evaluated with not enough accurate fitting results. Therefore, another evaluations for those 7 cases were required to be with more accuracy. Then, those coefficients were evaluated with enough accuracy. (2)It was verified that the macroscopic dispersion coefficient tend to be increased with increase of the average radius of tracer front. In some cases, however, the trend was not verified because of the limit of accuracy for data measured in the experiment and for the evaluation method of the coefficient. (3)It was found that the macroscopic dispersion coefficients evaluated for the cases with heterogeneous permeability field type B tend to be higher than those with heterogeneous permeability field type A.
; Watari, Shingo; Ijiri, Yuji*
JNC TN8400 99-094, 81 Pages, 1999/11
Safety assessment of the geological isolation system according to the groundwater scenario has traditionally been conducted based on the single canister configuration and then the safety of total system has been evaluated based on the dose rates which were obtained by multiplying the migration rates released from the engineered barrier and/or the natural barrier by dose conversion factors and total number of canisters disposed in the repository. The dose conversion factors can be obtained from the biosphere analysis. In this study, we focused on the effect of multiple sources due to the disposal of canisters at different positions in the repository. By taking the effect of multiple sources into consideration, concentration interference in the repository region is possible to take place. Therefore, radionuclide transport model/code considering the effect of concentration interference due to the multiple sources was developed to make assessments of the effect quantitatively. The newly developed model/code was verified through the comparison analysis with the existing radionuclide transport analysis code used in the second progress report. In addition, the effect of the concentration interference was evaluated by setting a simple problem using the newly developed analysis code. This results shows that the maximum peak value of the migration rates from the repository was about two orders of magnitude lower than that based on single canister configuration. Since the analysis code was developed by assuming that all canisters disposed of along the one-dimensional groundwater flow contribute to the concentration interference in the repository region, the assumption should be verified by conducting two or three-dimensional analysis considering heterogeneous geological structure as a future work.
Sawada, Atsushi; Ijiri, Yuji; *; Watari, Shingo
JNC TN8400 99-093, 58 Pages, 1999/11
This paper decribes the results of PA studies considering heterogeneous fracture characteristics, for the purpose of contributing for the performance assessment of the natural barrier system PA in H12 report (The second progress report on research and development for the Geological Disposal of HLW in Japan). In this study, 3-D discrete fracture network mode1 (DFN) and 1-D multiple pathways model is applied for 100m scale of rock block. Although nuclide release rate calculated by DFN are widely distributed among the realizations, it is shown that several tens realizations are enough number to understand the stochastic characteristics of the nuclide release. From the data uncertainty analysis, there are no significant effects for the nuclide retardation in fracture geometry parameters such as fracture radius, density and etc. 1-D multiple pathways model is developed with focusing on the heterogeneity of the transmissivity, which has a large effect to the nuclide retardation effects. The nuclide release rate calculated by using 1-D multiple pathways model approximates to the results of DFN. This result also shows that the relatively large fractures/faults that connects disposal tunnel and downstream faults have an important role for performance assessment in natural barrier system.
Ijiri, Yuji; ; *; Watari, Shingo; K.E.Web*; *; *
JNC TN8400 99-092, 91 Pages, 1999/11
JNC has been developed the performance assessment approaches for both fractured rock and porous rock. An equivalent continuum model is incorporated for solving the radionuclide migration in porous rock, while a discrete fracture network model is incorporated for solving the radionuclide migration in fractured rock (see more detail in Sawada et al. [1999]). This report describes the methodology, the data and the results of the performance assessment of porous rock. From the results of radionuclide migration analyses that were based on the hydrogeological properties obtained from the Neogene sedimentaly rock at the Tono mine, it was found that the release rate of selenium-79 and cesium-135 are dominant in porous rock. The sensitivity analyses using one-dimensional porous model revealed that hydraulic conductivity has more influences on the results than porosity does. In addition, it was found that smaller distribution coefficients of sandstone yield higher release rate than mudstone and tuff, and smaller distribution coefficients of saline water conditions yield higher release rate than fresh water conditions. The radionuclide migration in Neogene sedimentaly rock, where flow in rock matrix as well as in fractures are significant, was evaluated by superposing the results of porous model and fracture model. Since fracture model tends to yield more conservative results than porous model, it is obvious that the performance of Neogene sedimentary rock can be conservatively assessed by fracture model alone. The nuclide migration analyses performed in this report were based on the hydrogeological properties obtained at the depth between 20 meters and 200 meters frrom the ground surface. Therefore, it should be noted that the release rate at the depth of a future repository in Neogene sedimentary rock, 500 m, will be smaller than that shown in this report due to peemeability decrease from 200 m to 500 m.
Nakagawa, Kei*; Jinno, Kenji*; Ijiri, Yuji; Watari, Shingo; ; Uchida, Masahiro
JNC TY8400 99-005, 121 Pages, 1999/06
no abstracts in English
Jinno, Kenji*; Nakagawa, Kei*; *; *; Ijiri, Yuji*; *; Watari, Shingo
PNC TY1606 98-001, 54 Pages, 1998/03
no abstracts in English
Jinno, Kenji*; Nakagawa, Kei*; *; ; Ijiri, Yuji*; Watari, Shingo; Webb, E. K.*; Kanazawa, Yasuo*; Uchida, Masahiro
PNC TY1606 97-001, 44 Pages, 1997/03
no abstracts in English
Hatanaka, Koichiro; Watari, Shingo; Uchida, Masahiro; Takase, Hiroyasu*; Impey, M. D.*
Materials Research Society Symposium Proceedings, Vol.412, 739- Pages, 1996/00
None
Hatanaka, Koichiro; Watari, Shingo*; Kanazawa, Yasuo*; Uchida, Masahiro; Ishiguro, Katsuhiko; Ishikawa, Hirohisa
PNC TN8410 95-377, 57 Pages, 1995/11
None
Watari, Shingo*; Kitayama, Ayami; Mitsui, Seiichiro; Taniguchi, Naoki; Kimura, Wataru*; Kajiyama, Hiroshi*
no journal, ,
The application of pure copper is being considered for the purpose of extending the life-time of disposal canisters in the direct disposal of spent fuel. Pure copper generally shows little corrosion development in aqueous solution environments with low oxygen concentrations due to its thermodynamic stability, but pure copper loses thermodynamic stability and corrosion develops depending on the sulfides conditions. In this study, immersion tests and U-bend tests were conducted to understand the corrosion progress behavior and stress corrosion cracking behavior of pure copper under the condition of sparging gas with various hydrogen sulfide concentrations to simulate the disposal environment where sulfide exists.
