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Journal Articles

Development of fission product chemistry database ECUME for the LWR severe accident

Miwa, Shuhei; Miyahara, Naoya; Nakajima, Kunihisa; Nishioka, Shunichiro; Suzuki, Eriko; Horiguchi, Naoki; Liu, J.; Miradji, F.; Imoto, Jumpei; Mohamad, B. A.; et al.

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

We constructed the first version of fission product (FP) chemistry database named ECUME for LWR severe accident. The first version of ECUME is equipped with dataset of the chemical reactions and their kinetics constants for the reactions of cesium(Cs)-iodine(I)-boron(B)-molybdenum(Mo)-oxygen(O)-hydrogen(H) system in gas phase, the elemental model for the high temperature chemical reaction of Cs with stainless steel, and thermodynamic data for CsBO$$_{2}$$ vapor species and solids of Cs$$_{2}$$Si$$_{4}$$O$$_{9}$$ and CsFeSiO$$_{4}$$. The ECUME will provide more accurate estimation of Cs distribution due to the evaluation of effects of interaction with BWR control material B and stainless steel on Cs behavior in the Fukushima Daiichi Nuclear Power Station.

JAEA Reports

Memoirs; The Energy Technology Data Exchange (ETDE) for Japan

Kunii, Katsuhiko; Itabashi, Keizo; Yonezawa, Minoru

JAEA-Review 2019-002, 237 Pages, 2019/03


From 1987 to 2014, the Energy Technology Data Exchange (ETDE) Program under the auspices of the International Energy Agency (IEA) had been carried out successfully with fruitful outcomes. ETDE had been able to be an excellent database for use in the general field of application of energy, including nuclear energy. ETDE could have deserved it, by extensively collecting the literature and providing the metadata worldwide, as well as by delivering and disseminating the bibliographic data, first to member countries, next additionally to the developing countries free of charge and finally all the world through the Internet free of charge as well. During all the days of ETDE Program Then ETDE had been very close and strong ties and cooperation with the International Nuclear Information System (INIS) Program under the auspices of the International Atomic Energy Agency (IAEA), e.g., by sharing and complementing many elements and parts of each database mutually. A portal site, the ETDE World Energy Base (ETDEWEB), for the database of ETDE, had been available for use to deliver and disseminate the valuable information of bibliography of ETDE, containing directions to the full text data, dedicated to satisfying the interest of end users worldwide. As of today, even if the addition of bibliographic data to ETDE has ceased since 2014, ETDEWEB itself has been available as before, maintained in great help of the Office of Scientific and Technical Information (OSTI) of the Department of Energy (DOE), US, while OSTI had been praised as the Operating Agent (OA) of ETDE Program from the commencement to the ceasing. This is a report containing several historical documents in regard with the ETDE activities worldwide kept and remained in Japan as records (minutes etc) at the side of JAERI.

JAEA Reports

Update of JAEA-TDB; Update of thermodynamic data for zirconium and those for isosaccahrinate, tentative selection of thermodynamic data for ternary M$$^{2+}$$-UO$$_{2}$$$$^{2+}$$-CO$$_{3}$$$$^{2-}$$ system and integration with JAEA's thermodynamic database for geochemical calculations

Kitamura, Akira

JAEA-Data/Code 2018-018, 103 Pages, 2019/03


The latest available thermodynamic data were critically reviewed and the selected values were included into the JAEA-TDB for performance assessment of geological disposal of high-level radioactive and TRU wastes. This critical review specifically addressed thermodynamic data for (1) a zirconium-hydroxide system through comparison of thermodynamic data selected by the Nuclear Energy Agency within the Organisation for Economic Co-operation and Development (OECD/NEA), (2) complexation of metal ions with isosaccharinic acid based on the latest review papers. Furthermore, the author performed (3) tentative selection of thermodynamic data on ternary complexes among alkaline-earth metal, uranyl and carbonate ions, and (4) integration with the latest version of JAEA's thermodynamic database for geochemical calculations. The internal consistency of the selected data was checked by the author. Text files of the updated and integrated thermodynamic database have been prepared for geochemical calculation programs of PHREEQC and Geochemist's Workbench.

Journal Articles

Some characteristics of gas-liquid two-phase flow in vertical large-diameter channels

Shen, X.*; Schlegel, J. P.*; Hibiki, Takashi*; Nakamura, Hideo

Nuclear Engineering and Design, 333, p.87 - 98, 2018/07

 Times Cited Count:1 Percentile:62.02(Nuclear Science & Technology)

JAEA Reports

Development of a calculation method for atmospheric dispersion database that can immediately provide calculation results for any source term and period from hindcast to short-term forecast (Joint research)

Terada, Hiroaki; Tsuzuki, Katsunori; Kadowaki, Masanao; Nagai, Haruyasu; Tanaka, Atsunori*

JAEA-Data/Code 2017-013, 31 Pages, 2018/01


We developed an atmospheric dispersion calculation method that can respond to various needs for dispersion prediction in nuclear emergency and prepare database of information useful for planning of emergency response. In this method, it is possible to immediately get the prediction results for provided source term by creating a database of dispersion calculation results without specifying radionuclides, release rate and period except release point. By performing this calculation steadily along with meteorological data update, it is possible to immediately get calculation results for any source term and period from hindcast to short-term forecast. This function can be used for pre-accident planning such as optimization of monitoring plan and understanding events to be supposed for emergency response. Spatiotemporal distribution of radioactive materials reproduced by source term estimated inversely from monitoring based on this method is useful as a supplement to monitoring.

JAEA Reports

The Advisory Committee of International Nuclear Information System (INIS) for Japan

Kunii, Katsuhiko; Itabashi, Keizo

JAEA-Review 2016-021, 130 Pages, 2016/10


Under the International Atomic Energy Agency (IAEA), the International Nuclear Information System (INIS) Programme commenced in 1970 and ever since INIS has been acting as a database system available worldwide through information networks each time providing bibliographic information then full text documents of literature, technical reports, etc. on peaceful use of nuclear science and technology, thoroughly supported and maintained by INIS Secretariat in Vienna, on the other hand the inputs for INIS are provided by Member States and Organizations in their own boundaries. As for the INIS activity in Japan, while, the Japan Atomic Energy Research Institute (JAERI), then succeeded as the Japan Atomic Energy Agency (JAEA) as of today, the both have been responsible with the INIS activity in Japan as the INIS National Centre for Japan based on the request of the "former" Science and Technology Agency of the Japanese Government, an advisory committee had have a very important role for the INIS activity in Japan by enthusiastically advising the whole related to the activity from advanced and comprehensive viewpoints of expertise. This report describes about it, the Advisory Committee of International Nuclear Information System (INIS) for Japan, successfully been held 34 times from Oct. 1970 to Mar 2005. Included are the history and its records, change of the member and topics of the Advisory Committee, and the minutes.

JAEA Reports

Development of waste management system

Mitsuda, Motoyuki; Sasaki, Toshiki

JAEA-Technology 2015-013, 29 Pages, 2015/06


For implementation of disposal of the radioactive waste generated from Japan Atomic Energy Agency, Waste Management System which manages all of the waste data has been developed. We surveyed the kinds of data needed for the waste management at each site, and we set the standard waste management data items. We developed conceptual design for the waste management system and established the system for major sites, Nuclear Science Research Institute, Ningyo-toge Environmental Engineering Center, Fugen Decommissioning Engineering Center, Oarai Research and Development Center, Nuclear Fuel Cycle Engineering Laboratories. For other small sites, we accumulate waste data to the common waste storage database. Therefore, we have developed the system which manages the quality assurance waste data depending on waste treatment situation in JAEA.

Journal Articles

Applicability study of nuclear graphite material IG-430 to VHTR

Osaki, Hirotaka; Shimazaki, Yosuke; Sumita, Junya; Shibata, Taiju; Konishi, Takashi; Ishihara, Masahiro

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05

For the design on the VHTR graphite components, it is desirable to employ graphite material with higher strength. IG-430 graphite has been developed as an advanced candidate for VHTR. However, the new developed IG-430 does not have enough databases for the design of HTGR. In this paper, the compressive strength (Cs) of IG-430, one of important strengths for design data, is statistically evaluated. The component reliability is evaluated based on the safety factors defined by the graphite design code, and the applicability as the VHTR graphite material is discussed. It was found that IG-430 has higher strength (about 11%) and lower standard deviation (about 27%) than IG-110 which is one of traditional graphites used for HTGR, because the crack in IG-430 would not easy to propagate rather than IG-110. Since fracture probability for IG-430 is low, the higher reliability of core-component will be achieved using IG-430. It is expected that IG-430 is applicable for VHTR graphite material.

JAEA Reports

Report on research and development of nuclear forensics technologies

Okubo, Ayako; Kimura, Yoshiki; Shinohara, Nobuo; Toda, Nobufumi; Funatake, Yoshio; Watahiki, Masaru; Sakurai, Satoshi; Kuno, Yusuke

JAEA-Technology 2015-001, 185 Pages, 2015/03


Nuclear forensics is the analysis of intercepted illicit nuclear or radioactive material and any associated material to provide evidence for nuclear attribution by determining origin, history, transit routes and purpose involving such material. Nuclear forensics activity includes sampling of the illicit material, analysis of the samples and evaluation of the attribution by comparing the analyzed data with database or numerical simulation. Because the nuclear forensics technologies specify the origin of the nuclear materials used illegal dealings or nuclear terrorism, it becomes possible to identify and indict offenders, hence to enhance deterrent effect against such terrorism. Worldwide network on nuclear forensics can contribute to strengthen global nuclear security regime. In this paper, the results of research and development of fundamental nuclear forensics technologies performed in Japan Atomic Energy Agency during the fiscal term of 2011-2013 were reported.

Journal Articles

Production and compilation of charge changing cross sections of ion-atom and ion-molecule collisions

Imai, Makoto*; Shirai, Toshizo*; Saito, Manabu*; Haruyama, Yoichi*; Ito, Akio*; Imanishi, Nobutsugu*; Fukuzawa, Fumio*; Kubo, Hirotaka

Journal of Plasma and Fusion Research SERIES, Vol.7, p.323 - 326, 2006/00

no abstracts in English

Journal Articles

Development of Web-based RDB system in JAERI ERL-FEL

Kikuzawa, Nobuhiro; Nagai, Ryoji

Proceedings of 2nd Annual Meeting of Particle Accelerator Society of Japan and 30th Linear Accelerator Meeting in Japan, p.430 - 432, 2005/07

no abstracts in English

JAEA Reports

Development of control and data processing system for JAERI ERL-FEL

Kikuzawa, Nobuhiro

JAERI-Tech 2005-022, 48 Pages, 2005/03


no abstracts in English

Journal Articles

Hydrogen and hydration in proteins and nucleic acids; Neutron diffraction from bio-macromolecules at JAERI

Niimura, Nobuo; Arai, Shigeki; Kurihara, Kazuo; Chatake, Toshiyuki*; Tanaka, Ichiro*; Bau, R.*

Hydrogen- and Hydration-Sensitive Structural Biology, p.17 - 35, 2005/00

At the JAERI, we have constructed several high-resolution neutron diffractometers dedicated to biological macromolecules (called BIX-type diffractometers), which use a monochromatized neutron beam and a neutron imaging plate detector. In this paper, we review several interesting results regarding hydrogen positions and hydration in proteins, obtained using the two BIX-type diffractometers in JAERI. The general subject of neutron protein crystallography has been reviewed by several authors, and several selected topics have been discussed.

Journal Articles

Development of a knowledge based system linked to a materials database

Kaji, Yoshiyuki; Tsuji, Hirokazu; Fujita, Mitsutane*; Xu, Y.*; Yoshida, Kenji*; Mashiko, Shinichi*; Shimura, Kazuki*; Miyakawa, Shunichi*; Ashino, Toshihiro*

Data Science Journal (Internet), 3, p.88 - 94, 2004/07

The distributed material database system named "Data-Free-Way" has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute, and the Japan Science and Technology Corporation) under a cooperative agreement. In order to create additional values of the system, knowledge base system, in which knowledge extracted from the material database is expressed, is planned to be developed for more effective utilization of Data-Free-Way. XML (eXtensible Markup Language) has been adopted as the description method of the retrieved results and the meaning of them. One knowledge note described with XML is stored as one knowledge which composes the knowledge base. This paper describes the current status of Data-Free-Way, the description method of knowledge extracted from the material database with XML and the distributed material knowledge base system.

Journal Articles

Roles of aspect ratio, absolute $$B$$ and effective $$Z$$ of the H-mode power threshold in tokamaks of the ITPA database

Takizuka, Tomonori; ITPA H-mode Threshold Database Working Group*

Plasma Physics and Controlled Fusion, 46(5A), p.A227 - A233, 2004/05

 Times Cited Count:34 Percentile:22.88(Physics, Fluids & Plasmas)

To evaluate the H-mode power threshold in future tokamak reactors, quantitative scaling formulas have been developed by using the ITPA threshold database. Recently data from spherical tokamaks (MAST and NSTX) were supplied to the ITPA database. A new scaling expression, which includes the absolute magnetic field B instead of the toroidal magnetic field, subsumes the plasma current dependence at low aspect ratio and is consistent with the previous data without any explicit current dependence. Other possible influence of the low aspect ratio to increase the power threshold is also investigated. It is cralified for the whole data set that the effective charge number Z raises the power threshold. By adding Z as a parameter of the scaling expression, both the scattering nature and the low-density anomaly found in the experimental data can be reduced.

Journal Articles

A Review of internal transport barrier physics for steady-state operation of tokamaks

Connor, J. W.*; Fukuda, Takeshi*; Garbet, X.*; Gormezano, C.*; Mukhovatov, V.*; Wakatani, Masahiro*; ITB Database Group; ITPA Topical Group on Transport and Internal Barrier Physics*

Nuclear Fusion, 44(4), p.R1 - R49, 2004/04

 Times Cited Count:238 Percentile:23.26(Physics, Fluids & Plasmas)

This paper first reviews the present state of theoretical and experimental knowledge regarding the formation and characteristics of ITBs in tokamaks. Specifically, the current status of theoretical modeling of ITBs is presented; then, an international ITB database based on experimental information extracted from some nine tokamaks is described and used to draw some general conclusions concerning the necessary conditions for ITBs to appear, comparing these with the theoretical models. The experimental situation regarding the steady-state, or at least quasi-steady-state, operation of tokamaks is reviewed and finally the issues and prospects for achieving such operational modes in ITER are discussed.

JAEA Reports

A Development of a database system for the released radioactive gases and liquid from the nuclear facilities

Kikuchi, Masamitsu; Taki, Mitsumasa; Kume, Etsuo; Kobayashi, Hideo*; Yamada, Toshio*; Yamaguchi, Takenori

JAERI-Data/Code 2004-006, 146 Pages, 2004/03


The nuclear facilities, which are required to control the released radioactive gases and liquid, exist in Tokai research establishment as much as 40. These radioactive controls are carried out complying with the statutes in each facility. The released radioactivity data of each facility must be reported to MEXT and Ibaraki Prefecture from Tokai Research Establishment. This system is developed to make the database gathering the radioactivity data of each facilities for unitary control as Tokai Research Establishment and contribute to make the reports to MEXT and Ibaraki Prefecture.

Journal Articles

MOGRA-DB; Database system for migration prediction code MOGRA

Amano, Hikaru; Ikeda, Hiroshi*; Sasaki, Toshihisa*; Matsuoka, Shungo*; Kurosawa, Naohiro*; Takahashi, Tomoyuki*; Uchida, Shigeo*

KEK Proceedings 2003-11, p.239 - 244, 2003/11

A Code MOGRA (Migration Of GRound Additions) is a migration prediction code for toxic ground additions including radioactive materials in a terrestrial environment, which consists of computational codes that are applicable to various evaluation target systems, and can be used on personal computers. The computational code has the dynamic compartment analysis block at its core, the graphical user interface (GUI) for model formation, computation parameter settings, and results displays. The code MOGRA has varieties of databases, which is called MOGRA-DB. Another additional code MOGRA-MAP can take in graphic map and calculate the square measure about the target land.

Journal Articles

Improvements to SFCOMPO; A Database on isotopic composition of spent nuclear fuel

Suyama, Kenya; Nouri, A.*; Mochizuki, Hiroki*; Nomura, Yasushi*

JAERI-Conf 2003-019, p.890 - 892, 2003/10

Isotopic composition is one of the most relevant data to be used in the calculation of burnup of irradiated nuclear fuel. Since autumn 2002, the Organisation for Economic Co-operation and Development/Nuclear Energy Agency OECD/NEA) has operated a database of isotopic composition; SFCOMPO, initially developed in Japan Atomic Energy research Institute. This paper describes latest version of SFCOMPO and the future development plan in OECD/NEA.

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