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Murakami, Masashi; Sasaki, Toshiki
JAEA-Review 2022-004, 106 Pages, 2022/06
JAEA-Review-2022-004.pdf:3.95MB
A numerous analytical data will be required for the characterization of the radioactive waste stored in Japan Atomic Energy Agency toward their processing and disposal. A "Data Quality Objectives (DQO) Process" is widely applied as a tool for the development of a cost-effective characterization plan in the overseas nuclear sites. The DQO Process is a multi-step planning process developed by the United States Environmental Protection Agency (EPA), and can be used for the planning of a scientifically rigorous and cost-effective data collection program for the various projects involving the collection of the environmental data. We have considered to reduce the cost required for the future characterization of the stored waste by applying the statistical methods and have performed a literature survey on the DQO Process. The survey effort was focused on the guidance documents of the DQO Process published by the EPA and was also spent for the related matters such as a quality system of the EPA and the activities beyond the DQO Process as well as the examples of the application at the nuclear sites. In this report, the details on the planning procedure using the DQO Process are reviewed together with the background information such as why DQO Process was developed, what kind of transition was occurred, and how it is currently used in the EPA. The examples on the application for various objects at Hanford Site in the United States, where has the various legacy waste generated in the past activities and has the big environmental problems, are also reviewed. This report summarizes the important matters and methodology on the planning with the statistical sampling methods. It also provides the examples of the approaches for the complex objects, and will therefore be helpful in the future planning for the various kind of the waste characterization.
Kumazaki, Yui
Karento Aweanesu-E (Internet), (364), p.E2108_1 - E2108_2, 2019/02
no abstracts in English
Saito, Hiroshi
JAEA-Review 2016-009, 80 Pages, 2016/07
JAEA-Review-2016-009.pdf:8.28MB
Environmental remediation has been conducted in closed Ningyo-toge Uranium Mine, after decades of mine-related activities. During the remediation, whole procedure, priority, necessary investigations and specific methods have been examined, and issues are clarified which should be solved in the future. For that, it has been recommended that opinions are exchanged among specialists in related fields overseas, and information and their experience are referred. As part of the activities, Ningyo-toge Environmental Engineering Center has been involved continuously in IAEA ENVIRONET, multinational network for environmental remediation. Also, bonds are tightened among participants and IAEA by exchanging opinions and sharing the issues. In parallel, literature survey has been conducted to supplement the information obtained through ENVIRONET and to clarify additionally-required information and targeted sites. The expected information are obtained from the site-visits and now being organized.
Ikeda, Kiyoshi; Gonda, Mayuki; Nagaya, Shun; Hayakawa, Misa; Kunii, Katsuhiko; Mineo, Yukinobu; Yonezawa, Minoru; Itabashi, Keizo
Proceedings of 16th International Conference on Grey Literature (GL-16), p.139 - 145, 2015/03
The Japan Atomic Energy Agency (JAEA) Library has collected Internet information related the Fukushima Accident. We previously reported the development of the Fukushima Accident Archive using the DSpace in 15th International Conference on Grey Literature. We have encountered a new challenging issue grey literature. In many cases, Internet information contains valuable numerical data. However, it is difficult to identify the existence of numerical data in the Internet sites because numerical data is not often organized in a systematic manner on the web sites. We considered such method as to identify numerical data and attempted to introduce "data flagging" system, which was previously used in the International Atomic Energy Agency's International Nuclear Information System (INIS). In this presentation, we will introduce our "data flagging" system for numerical data on the Internet and how we apply the system to our Fukushima Accident Archive.
Ikeda, Kiyoshi
Joho No Kagaku to Gijutsu, 55(5), p.219 - 223, 2005/05
Conference proceedings are information resources used for researchers to access latest research trends. Although they are important materials that should be collected by the library, it is generally very difficult to acquire them because they are not commercially available. JAERI (Japan Atomic Energy Research Institute) Library collects about 19,000 proceedings and makes them available for the researchers. This paper introduces JAERI Library's experience in acquiring conference proceedings in a variety of ways including collecting conference information from academic societies or researchers, utilizing INIS (International Nuclear Information System) database as well as provision of conference proceedings. JAERI-Conf series, which are the proceedings of conferences hosted by JAERI and published as JAERI's research reports, are also introduced.
Ishikawa, Masashi; Habara, Tadashi; Oshima, Takeshi
Joho No Kagaku to Gijutsu, 54(3), p.126 - 132, 2004/03
no abstracts in English
Nakajima, Hidemitsu
Senmon Toshokan, (200), p.11 - 12, 2003/07
no abstracts in English
Sugita, Yutaka; Yui, Mikazu
JNC TN8450 2001-007, 16 Pages, 2002/02
JNC-TN8450-2001-007.pdf:0.78MB
This report summary the dataset of the relationship between unconfined compressive strength and tensile strength of the rock mass described in supporting report 2; repository design and engineering technology of second progress report (H12 report) on research and development for the geological disposal of HLW in Japan.
Kato, Hiroshige*; Mine, Tatsuya*; Mihara, Morihiro; Oi, Takao; Honda, Akira
JNC TN8400 2001-029, 63 Pages, 2002/01
JNC-TN8400-2001-029.pdf:1.81MB
Cementitious materials will be used for the TRU waste repository as a component of engineered barrier system. The distribution coefficients which represent the retardation of radionuclides migration for the cementitious materials would be one of the important parameter for the safety assessment. The much information of radionuclide sorption onto the cementitious materials has been accumulated through the study in the world. Therefore it is necessary to compile the information and Kd of the radionuclides reported in previous studies. In this report, the Kd of the important radionuclides, such as C, Ni, Se, Sr, Zr, Nb, Mo, Tc, Sn, I, Cs, Sm, Pb, Ra, Ac, Th, Pa, U, Np, Pu, Am, Cm, for the cementitious materials were compiled as the Sorption Database (SDB). For radionuclides to be sensitive to the redox potential, e.g. Se, Tc, Pa, U, Pu and Np, some Kds measured under the controlled atmosphere had been reported, and few Kds measured under the controlled redox potential had been reported. For Se, Mo, Sm, Cm and Ac, the distribution coefficients had not been reported, therefore distribution coefficients of Se and Mo for OPC (Ordinary Portland Cement) pastes were measured by batch sorption experiments and these data were added into the SDB.
; ; ; Omori, Eiichi
JNC TN8410 2001-021, 33 Pages, 2001/09
JNC-TN8410-2001-021.pdf:4.37MB
Carbon-14 released from the nuclear facilities is an important radionuclide for the safety assessment, because it tends to accumulate in environment through food chain and has as a significant impact to personal dose. Carbon-14 has been monitored routinely as one of the main gaseous radionuclides exhausted from the Tokai Reprocessing Plant (TRP) since OCtober of 1991. Furthermore, behavior of carbon-14 in TRP has been investigated through the reprocessing operation and the literature survey. This report describes the result of investigation about the behavior of carbon-14 in TRP as followings. (1)Only a very small amount of carbon-14 in the fuel was liberated into the shear off-gas and most of it was liberated into the dissolver of-gass. Part of the carbon-14 was trapped at the caustic scrubber installed in the of-gas treatment process, and untrapped carbon-14 was released into the environment from the main stack. Amount of carbon-14 released from the main stack was about 4.1
6.5GBq every ton of uranium reprocessed. (2)Carbon-14 trapped at the caustic scrubbers installed in the dissolver off-gas and in the vessel off-gas treatment process is transferred to the low active waste vessel. Amount of carbon-14 transferred to the low active waste vessel was about 5.4 9.6GBq every ton of uranium reprocessed. (3)The total amount of carbon-14 input to TRP was summed up to about 11.915.5 GBq every ton of uranium reprocessed considering the released amount from the main stack and the trapped amount in the off-gas treatment devices. The amount of nitrogen impurity in the initial fuel was calculated about 1522ppm of uranium metal based on the measured carbon-14. (4)The solution in the low active waste vesselis concentrated at the evaporator.Most of the carbon-14 in the solution was transferred into concentrated solution. (5)Tokai vitrification Demonstration Facility (TVF) started to operate in 1994. Since then, carbon-14 has been measured in the ...
Takebe, Shinichi; Abe, Masayoshi
JAERI-Data/Code 2001-005, 344 Pages, 2001/03
JAERI-Data-Code-2001-005.pdf:10.79MB
no abstracts in English
Kofuji, Hirohide; ; *; *;
JNC TN9400 2000-055, 49 Pages, 2000/03
JNC-TN9400-2000-055.pdf:2.07MB
Accompanying with the progress of the "Feasibility study on FBR cycle system; FS" , various kinds of technical information, facility design parameters, and related data will be obtained and they should be stored in data bases and be used as fundamental data for the FS. So the several data bases are going to be set up at each section and controlled by the management system through a local area network. Among above data bases, a prototype of FBR cycle data base that will record data for FBR scenario study and synthetic assessment is to be completed in. Phase l by fiscal year 2000, so the data base system concept has been examined in the current fiscal year, 1999. As the results of the system concept examination, two types of prototypes have been selected, one is to be set up as the data table containing digital data that are extracted from technical papers, another is as image data of papers with index information. Referring to examples of data bases in other companies, it was kept in mind to use a package software for general purpose and to utilize data existing now.
; Sato, Wakaei*;
JNC TN9400 2000-037, 87 Pages, 2000/03
JNC-TN9400-2000-037.pdf:3.48MB
ln order to compare the nuclear characteristics of water-cooled bleeder cores with that of LMFBR, MOX fuel cell models are established for boiling and non-boiling LWR, non-boiling HWR and sodium-cooled reactor. Frst, the comarison is made between the heterogeneous cell calculation results by SRAC and those by SLAROM. The results show some differences as for neutron energy spectrum, one-grouped cross section and conversion ratio due to the different grouped cross section library (both are based on JENDL-3.2, though) used for each code, however, the difference is acceptably small for grasping the basic characteristics of the above-mentioned cores. Second, using the SLAROM code, main core parameters such as mean neutron energy, ratio of fast neutron and 
-value, are analyzed. The comparison between the cores show that softened neutron spectrum by the scattering effect of hydrogen or heavy hydrogen increase the contribution of nuclear reaction (especially for neutron capture reaction rather than fission reaction) in lower energy region comparing with LMFBR. ln order to overcome the effect, tighter lattice than LMFBR is necessary for water-cooled cores to realize the breeding of fissile nuclides. Third, effects of Pu isotopic composition on the breeding ratio are evaluated using SRAC burnup calculation. From the results, it is confirmed that degraded Pu (larger ratio of Pu-240) show the larger breeding ratio. At last, sensitivity analyses are made for k-effective and main reaction ratios. As for k-effective, using a temporary covariance data of JENDL-3.2, uncertainty resulting from the cross sections' error is analyzed for a boiling LWR and a sodium-cooled reactor. The boiling LWR core shows larger sensitivity in lower energy region than the sodium-cooled reactor (especially for the energy region lower than 1kev), And, 18-group analysis that is considered acceptably good for LMFBR analysis, should not be enough for accurate sensitivity estimation of ...
Shirakawa, Noriyuki*; *; *; *
JNC TJ9440 2000-008, 47 Pages, 2000/03
JNC-TJ9440-2000-008.pdf:1.96MB
The numerical thermohydraulic analysis of a LMFR component should involve its whole boundaly in order to evaluate the effect of chemical reaction within it. Therefore, it becomes difficult mainly due to computing time to adopt microscopic approach for the chemical reaction directly. Thus, the thermohydraulic code is required to model the chemically reactive fluid dynamics with constitutive correlations. The reaction rate denpends on the binary contact areas between components such as continuous liquids, droplets, solid particles, and bubbles. The contact areas change sharply according to the interface state between components. Since no experiments to study the jet flow with sodium-water chemical reaction have been done, the goal of this study is to obtain the knowledge of flow regimes and contact areas by analyzing the fluid dynamics of multi-pahse and reactive components mechanistically with the particle interaction method. For the first stage of the study, the applicability of this method to the nalysis of a liquid jet into the other liquid pool was investigated. Based on the literatures, we investigated the jet flow mechanisms and analyzed the experiment of a water jet into a gasoline pool. We also analyzed SWAT3/Run19 test, the jet flow in a rod bundle, to study the applicability of the method to a complicated boundary without a chemical reaction model. The calculated fluid dynamics was in good agreement with the experiment. Furthermore, we studied and formulated the paths of phase change and chemical reaction, and conceptually designed the adopting the heat-transfer-limited phase change model and the synthesizd reaction model with a water-hydrogen conversion ratio.
*; *; *; *
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.
*; *
JNC TJ8420 2000-010, 171 Pages, 2000/03
JNC-TJ8420-2000-010.pdf:5.34MB
no abstracts in English
Toida, Masaru*; Shiogama, Yukihiro*; Atsumi, Hiroyuki; Masumoto, Kazuhiko*; Yasui, Shingo*; Abe, Yasunori*; Furuichi, Mitsuaki*
JNC TJ7440 2000-006, 137 Pages, 2000/02
JNC-TJ7440-2000-006.pdf:3.55MB
no abstracts in English
Miki, Takahito*; Sasamoto, Hiroshi; Chiba, Tamotsu*; Inagaki, Manabu*; Yui, Mikazu
JNC TN8400 2000-007, 32 Pages, 2000/01
JNC-TN8400-2000-007.pdf:0.69MB
This report presents a summary of literature survey about geochemical reactions which are important to evaluate the redox conditions in the near field rock mass and buffer. The results of literature survey are summarized as follows; (1)Minerals including ferrous iron and organic materials in the rock mass are important reductants. Initial stage after closure of repository, oxygen will be consumed by pyrite, because the reaction rate between pyrite and oxygen is relatively fast. (2)It is possible to estimate the redox capacity for reductants by rock (mineral)-water iteraction experiment in a laboratory. And it is expected that the ferrous iron-rich rock and higher porosity rock may have bigger redox capacity. (3)It is possible to estimate the oxygen consumption rate by reductants such as minerals including ferrous iron. The rate law and rate constant for the oxidation reaction of ferrous iron in the solution are also determined. As a conclusion, it seems that we can evaluate kinetically the evolution of geochemical conditions in the near field rock mass and buffer by excavation of drifts, based on data derived from these existing literatures.
Arthur, R. C,*; Savage, D.*; Sasamoto, Hiroshi; Shibata, Masahiro; Yui, Mikazu
JNC TN8400 2000-005, 61 Pages, 2000/01
JNC-TN8400-2000-005.pdf:2.83MB
Kinetic data, including rate constants, reaction orders and activation energies, are compiled for 34 hydrolysis reactions involving feldspars, sheet silicates, zeolites, oxides, pyroxenes and amphiboles, and for similar reactions involving calcite and pyrite. The data are compatible with a rate law consistent with surface reaction control and transition-state theoly, which is incorporated in the geochemieal software package EQ3/6 and GWB. Kinetic data for the reactions noted above are strictly compatible with the transition-state rate law only under far-from-equilibrium conditions. It is possiblethat the data are conceptually consistent with this rate law under both far-from-equilibrium and near-to-equilibrium conditions, but this should be confirmed whenever possible through analysis of original experimental results, Due to limitations in the availability of kinetic data for mineral-water reactions, and in order to simplify evaluations of geochemical models of groundwater evolution, it is convenient to assume local-equilibrium in such models whenever possible. To assess whether this assumption is reasonable, a modeling approach accounting for coupled fluid flow and water-rock interaction is described that can be used to estimate spatial and temporal scale of local equiliblium. The approach is demonstrated for conditions involving groundwater flow in fractures at JNC's Kamaishi in-situ tests site, and is also used to estimate the travel time necessary for oxidizing surface waters to migrate to the level of a HLW repository in crystalline rock. The question of whether local equilibrium is a reasonable assumption must be addressed using an appropriate modeling approach. To be appropriate for conditions at the Kamaishi site using the modeling approach noted above, the fracture fill must closely approximate a porous medium, groundwater flow must be purely advective and diffusion of solutes across the fracture-host rock boundary must not occur. Moreover, the ...
Sato, Toshinori; Taniguchi, Wataru; Fujita, Tomoo; Hasegawa, Hiroshi
JNC TN7400 99-011, 36 Pages, 1999/12
In order to understand the general thermal and mechanical properties of rock masses and initial stress of rock at depth, data were compiled from the published literature in Japan and collected from investigations carried out at Kamaishi mine and Tono mine. Statistical examinations derived the ranges, means and medians of the mechanical properties for the different rock types. It was confirmed that the correlations between the mechanical properties were in agreement with correlations determined previously in other similar surveys. The unconfined compressive strength of Neogene sedimentary rocks showed a tendency to increase with increasing depth (
500 m). An examination of the measured initial stress data collected through literature surveys showed that the vertical stress can be approximated by the extent of gravitational loading at a particular point. There is an approximately linear relationship between the average stress in a horizontal plane and the depth. The lateral pressure coefficient tends to have a high value and large range at shallow depths, but tends towards 
1 with increasing depth.
