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Journal Articles

FaCT Phase-I evaluation on the advanced aqueous reprocessing process, 3; Highly effective dissolution technology for FBR MOX fuels

Ikeuchi, Hirotomo; Katsurai, Kiyomichi*; Sano, Yuichi; Washiya, Tadahiro

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Journal Articles

Development of simulation code for FBR spent fuel dissolution with rotary drum type continuous dissolver

Sano, Yuichi; Katsurai, Kiyomichi; Washiya, Tadahiro; Koizumi, Tsutomu; Matsumoto, Satoshi*

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10

Japan Atomic Energy Agency has been studying rotary drum type continuous dissolver for FBR spent fuel dissolution. For estimating the fuel dissolution behavior under several operational conditions in this dissolver, we have been developed the simulation code, PLUM, which mainly consists of 3 modules for calculating chemical reaction, mass transfer and thermal balance in the rotary drum type continuous dissolver.

JAEA Reports

Study on technical issues of site release of nuclear power plants; Criteria for site release, procedures and verification requirements based on experiences in the U.S. (Contract research)

Sukegawa, Takenori; Shimada, Taro; Katsurai, Kiyomichi; Tanaka, Tadao; Nakayama, Shinichi

JAEA-Review 2009-075, 86 Pages, 2010/03

JAEA-Review-2009-075.pdf:8.13MB

In the field of safety regulation systems for nuclear facilities after completion of operation, criteria of residual radioactivities and confirmation and verification procedures for termination of decommissioning are important problems that should concretely be made a study. Safety standards and criteria in IAEA, USA, etc., and practical examples of site release of power reactors in USA were studied, therefore, problems for introducing the regulation system in Japan were discussed. In this report, final status survey of Trojan power plant were investigated as a particular case of site release, and, concept of specifying survey areas to be measured radioactivities and demonstrated to compliance with release criteria was discussed. In addition, the idea of confirmation and verification procedure for termination of decommissioning in Japan was proposed referring to the US guidance (MARSSIM).

Journal Articles

Analysis of sludge in the dissolver and survey of the behavior of zirconium molybdate

Kondo, Yoshikazu; Uchida, Naoki; Terunuma, Hirotaka; Tanaka, Kosuke; Oyama, Koichi; Katsurai, Kiyomichi; Washiya, Tadahiro

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.277 - 280, 2009/09

The composition of sludge in the dissolver after dissolution of PWR and ATR fuels at the Tokai Reprocessing Plant (TRP) was analyzed. As a result the presence of zirconium molybdate was confirmed by the analysis of X-ray diffraction (XRD). To clarify the formation behavior of the precipitates of zirconium molybdate, investigated the dependence of HNO$$_{3}$$ concentration on the precipitation with Mo and Zr solution. To evaluate the adhesion on the metal surface (stainless steel and Ti metal), the deposition amounts of the precipitates of zirconium molybdate on the metal were also examined. In addition, it reports on the comparative result of executing a chemical dissolution of the precipitates by using the solutions of NaOH, C$$_{2}$$H$$_{2}$$O$$_{4}$$-HNO$$_{3}$$ and H$$_{2}$$O$$_{2}$$-HNO$$_{3}$$.

JAEA Reports

Investigation on future nuclear power reactors and fuel cycle systems

Otaki, Kiyoshi*; Tanaka, Yoji*; Katsurai, Kiyomichi*; Aoki, Kazuo*

JAERI-Review 2005-035, 79 Pages, 2005/09

JAERI-Review-2005-035.pdf:4.57MB

In order to collect technical information for the assessment on future nuclear power reactors and fuel cycle systems in Japan, investigation has been made on the characteristics and performance of future reactor options including reduced moderation water reactors (RMWRs) and their fuel cycle systems since the fiscal year 1998. The subjects of investigation are divided into three categories; breeder reactors and their fuel cycle, alternative to sodium-cooled FBR systems,plutonium recycling, spent fuel reprocessing and waste disposal. This report is a summary of the investigation carried out so far.

JAEA Reports

Study on solubility and leaching property of Iodine-129 waste-forms for geological disposal

Yanagisawa, Ichiro*; Katsurai, Kiyomichi*; Izumi, Jun*; Saigusa, Moriyuki*; *; *; *; Ueta, Shinzo*

JNC TJ8400 2000-038, 202 Pages, 2000/02

JNC-TJ8400-2000-038.pdf:15.12MB

(1)Sodalite and tourmaline are natural-occurring minerals, which can contain halide in their aluminosilicate lattices. Therefore, these materials have possibilities of immobilization of I-129. In this study, solubility measurements for these materials were carried out. It was confirmed from dissolution behaviors obtained for some kinds of sodalite and calculated results of solubilities based on thermodynamic data that dissolution of sodalite to aqueous solution could be limited by its solubility. Solubility of sodalite had tendencies of "synthesized one $$>$$ natural one" and "chloride $$>$$ iodide". Immobilized iodine in sodalite crystalline lattice was not replaced by chlolide ion in the solution. It was indicated that tourmaline has a possibility as a waste material containing I-129 from comparison of dissolution behavior of element with sodalite. (2)Leaching property of a multi-layered waste-form, that is composed of (1)iodine bearing material (zeolite), (2)coating layer (silica and apatite) and 3)low solubility matirx (apatite), was studied under reducing condition. The following results were obtained by the leaching experiments: (1)The coating layer of hidroxyapatite can reduce the iodine leaching rate by 4 order compared with that of bare iodine bearing material. (2)Ca and P concentration after one-month dipping reached the solubility estimated by the theoretical calculation using PHREEQE code. As a conclusion, it was indicated that this waste-form concept has potential to show low leaching rate.

JAEA Reports

Study on solubility and leaching property of iodine-129 waste-forms for geological disposal

Yanagisawa, Ichiro*; Katsurai, Kiyomichi*; Izumi, Jun*; Saigusa, Moriyuki*; Kitao, Hideo*; Tsuzuki, Yasuo*; Neyama, Atsushi*; Kato, Hiroyasu*; Nakazawa, Toshiyuki*; Okada, Kenichi*

JNC TJ8400 2000-037, 61 Pages, 2000/02

JNC-TJ8400-2000-037.pdf:2.78MB

no abstracts in English

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.

JAEA Reports

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

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

JNC TJ8400 2000-027, 28 Pages, 2000/02

JNC-TJ8400-2000-027.pdf:0.76MB

no abstracts in English

JAEA Reports

Reliability study on the assessment method for the geochemical phenomena of geological disposal

*; Katsurai, Kiyomichi*; Saigusa, Moriyuki*; *; Kitao, Hideo*; Tsuzuki, Yasuo*

JNC TJ8400 2000-012, 333 Pages, 2000/02

JNC-TJ8400-2000-012.pdf:11.14MB

In this study, technical review, laboratory experiment and modeling calculations were implemented in order to reliability of geochemical assessment technique for the second progress report. The summary of this study is as follows: (1)We have implemented the technical review of the second progress backup report geochemical modeling and some data. We have extracted a subject about groundwater evolution modeling and thermodynamic data. (2)We have implemented multivariable analysis based on database of deep groundwater sampled in geoscientofic investigation in other countries. We have considered validity of peculiar model groundwater of SRLP, FRLP and MRNP. (3)We have researched on redox reaction of a coastal sedimentary layer, and was cleared geochemical mechanism of dedox reaction. (4)We have studied thermodynamic of Se in laboratory. We have confirmed condition, which SRB was not in experimental system, initial solid transformed to solid phase (FeSe). And we have clarified chemical species of Se in the liquid phase. (5)We have researched on degradation of the engineered barrier material. We have prepared natural analogue data set that related to the iron and cooper. And we have acquired basic property of buffer material (Kunipia-F) in laboratory. (6)We have studied on dissolution kinetic of UO$$_{2}$$ in order to extract geochemistry technical factor for site selection. The dissolution rates in oxidized groundwater may be much slower than previously believed by most scientists. Therefore, oxidized environments, as well as reduced environments, may be considered as possible sites for underground repository sites.

JAEA Reports

Reliability study on the assessment method for the geochemical

*; Katsurai, Kiyomichi*; Saigusa, Moriyuki*; *; Kitao, Hideo*; Tsuzuki, Yasuo*

JNC TJ8400 2000-011, 65 Pages, 2000/02

JNC-TJ8400-2000-011.pdf:2.95MB

no abstracts in English

JAEA Reports

Experimental study on the solubility of selenium under simulated disposal conditions

Tachikawa, Hirokazu*; Kitao, Hideo*; Katsurai, Kiyomichi*; Yanagisawa, Ichiro*; Shibata, Masahiro; Suyama, Tadahiro*; Yui, Mikazu

JNC TN8400 99-068, 108 Pages, 1999/11

JNC-TN8400-99-068.pdf:3.59MB

In an evaluation of high level waste (HLW) repository performance, Se-79 is one of important elements to be analyzed. Selenium solubility and solubility limiting solid phase is not clear. Then, we performed solubility measurement tests from over saturation direction under reducing conditions considering the repository conditions in deep underground. In some cases, bentonite (Kunigel V1) or pyrite coexisted in the experimental system to simulate the repository conditions. Se bearing solids were determined by XRD analysis, and solubility limiting solid phase was discussed. FeSe$$_{2}$$ (Ferroselite) and Se (hexagonal) were identified in the simple condition test, in which Fe(II) solution and Se solution were mixed. SeS was also identified when S(-II) solution was added. The Se concentrations in aqueous phase were approximately 10$$^{-8}$$ mol/l at neutral pH and approximately 10$$^{4}$$ mol/l at pH9 in the bentonite coexisting tests and pyrite coexisting tests. The solid phases identified in the pyrite coexisting tests were mainly Se(hexagonal) and FeSe$$_{2}$$ (Ferroselite) in one of the samples. Further, the possibility of Fe(S,Se) solid solution formation was presumed on the pyrite surface dipping in the test solutions. In addition, we performed another selenium solubility measurement to accelerate the transformation of Se bearing solid phase at elevated temperature (80$$^{circ}$$C). The concentration of Se decreases with time and reached to the detection limit of ICP-MS (4$$times$$10$$^{-9}$$ mol/1) in 3 months. At first, Se(hexagonal) is dominant in the precipitation, however this solid phase was gradually transformed to Fe-Se solids (FeSe, FeSe$$_{2}$$) with time. Therefore it is strongly suggested that FeSe$$_{2}$$ which is the thermodynamically most stable phase will be a solubility limiting solid phase under repository conditions in long term. As the experimental system was confirmed as sulfate reducing bacteria free, it should be noted that whole observed reactions ...

JAEA Reports

Development study on the geological database (II)

*; *; Ida, Toshio*; Fusaeda, Shigeki*; *; Katsurai, Kiyomichi*

JNC TJ8400 99-039, 1926 Pages, 1999/02

JNC-TJ8400-99-039.pdf:54.31MB

This study has been carried out in order to increase the reliability of the performance assessment of geological isolation systems for high level wastes. We have been investigating a proper modeling of various phenomena, which would occur in the disposal environment and improving the reliability of geochemical data used in the performance assessment. The results are summarized as follows: (1)Quality assurance for geochemical data and modeling. We have compiled technical report, geochemical database (newest thermodynamic database), and calculation, conversion program for geochemical analysis, which supporting the second progress report. (2)Study on groundwater categorization and dominant reaction based on site data. We have carried out HCA/PCA analysis based on observed deep groundwater to support groundwater categorization of the second progress report. We concluded 3-type model groundwater categorized by analysis. (3)Experimental study on thermodynamic data of Se and Pd. It is confirmed that sulfate reduction bactelia do not exist in our experimental environment. (4)Planning on data acquisition for geochemical data of radioactive elements. Firstly we have pick up key radioactive elements and future studies based on the second progress report. Then we have draw up R&D plan for QUALITY. (5)Geochemical study on the long-term stability of backfill matelial. An extensive literature review was carried out about the effect of Iron on Bentonite stability. Experimental conditions are researched to develop thermodynamic and kinetic modeling. (6)Study on the technical geochemistry guideline of site selection for disposal. We have researched on the recommendation of sites for HLW (guideline of site selection) in foreign country and site selection from a view point of natural analogue. And we have summarized geochemistry technical guideline for site selection.

JAEA Reports

Development study on the geological database (II)

*; *; Ida, Toshio*; Fusaeda, Shigeki*; *; Katsurai, Kiyomichi*

JNC TJ8400 99-038, 59 Pages, 1999/02

JNC-TJ8400-99-038.pdf:1.65MB

This study has been carried out in order to increase the reliability of the performance assessment of geological isolation systems for high level wastes. We have been investigating a proper modeling of various phenomena, which would occur in the disposal environment and improving the reliability of geochemical data used in the performance assessment. The results are summarized as follows: (1)Quality assurance for geochemical data and modeling. We have compiled technical report, geochemical database (newest thermodynamic database), and calculation, conversion program for geochemical analysis, which supporting the second progress report. (2)Study on groundwater categorization and dominant reaction based on site data. We have carried out HCA/PCA analysis based on observed deep groundwater to support groundwater categorization of the second progress report. We concluded 3-type model groundwater categorized by analysis. (3)Experimental study on thermodynamic data of Se and Pd. It is confirmed that sulfate reduction bacteria do not exist in our experimental environment. (4)Planning on data acquisition for geochemical data of radioactive elements. Firstly we have pick up key radioactive elements and future studies based on the second progress report. Then we have draw up R&D plan for QUALITY. (5)Geochemical study on the long-term stability of backfill material. An extensive literature review was carried out about the effect of Iron on Bentonite stability. Experimental conditions are researched to develop thermodynamic and kinetic modeling. (6)Study on the technical geochemistry guideline of site selection for disposal. We have researched on the recommendation of sites for HLW (guideline of site selection) in foreign country and site selection from a view point of natural analogue. And we have summarized geochemistry technical guideline for site selection.

Oral presentation

Efficient dissolution development of FBR MOX fuel, 1; Outline of dissolution development in FaCT project

Oyama, Koichi; Katsurai, Kiyomichi; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 3; Evaluation of pressure increase by dissolution reaction in dissolver

Oyama, Koichi; Katsurai, Kiyomichi; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka; Nagata, Masanobu*; Horiuchi, Nobutake*; Chikazawa, Takahiro*; Kikuchi, Toshiaki*

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel

Oyama, Koichi; Katsurai, Kiyomichi; Nomura, Kazunori; Takeuchi, Masayuki; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 5; Endurance test of the bearing for rotary dram type continuous dissolver

Katsurai, Kiyomichi; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Takizawa, Takeyuki*; Yamashita, Kazuhiko*

no journal, , 

This report presents a knowledge getting from endurance test of the bearing for rotary dram type continuous dissolver which is under development as one of the Fast Reactor Cycle technology Development Project in JAEA. Non lubricant type bearing is preferable to endure heavy radiation environment but abrasion of the bearing is concerned due to heavy weigh and low swing motion. Small scale of the endurance test of the bearing using 4 types of candidates including all-ceramics and hybrid ceramics roll bearing, carbon slide bearing and air bearing was implemented. This report demonstrates the test results of the screening and a way of the improvement for select one.

Oral presentation

Development of sludge management technology on FBR fuel reprocessing, 1; Removal experiment of zirconium molybdate

Kondo, Yoshikazu; Katsurai, Kiyomichi; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

To investigate the chemical washing method of zirconium molybdate, the washing character using NaOH, C$$_{2}$$H$$_{2}$$O$$_{4}$$ and H$$_{2}$$O$$_{2}$$ were examined using the simulated solution of fuel dissolution process. Also we evaluated the deposition amounts of zirconium molybdate on the metal surface in the simulated solution.

Oral presentation

Development of highly effective dissolution technology for FBR MOX fuels

Ikeuchi, Hirotomo; Katsurai, Kiyomichi; Kondo, Yoshikazu; Sano, Yuichi; Washiya, Tadahiro; Koizumi, Tsutomu

no journal, , 

no abstracts in English

24 (Records 1-20 displayed on this page)