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Suyama, Kenya; Ueki, Taro; Gunji, Satoshi; Watanabe, Tomoaki; Araki, Shohei; Fukuda, Kodai; Yamane, Yuichi; Izawa, Kazuhiko; Nagaya, Yasunobu; Kikuchi, Takeo; et al.
Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 6 Pages, 2023/10
To remove and store safely the fuel debris generated by the severe accident of the Fukushima Daiichi Nuclear Power Station in 2011 is one of the most important and challenging topics for decommissioning of the damaged reactors in Fukushima. To validate the adopted method for the evaluation of criticality safety control of the fuel debris through comparison with the experimental data obtained by the criticality experiments, the Nuclear Regulation Authority (NRA) of Japan funds a research and development project which was entrusted to the Nuclear Safety Research Center (NSRC) of Japan Atomic Energy Agency (JAEA) from 2014. In this project, JAEA has been conducting such activities as i) comprehensive computation of the criticality characteristics of the fuel debris and making database (criticality map of the fuel debris), ii) development of new continuous energy Monte Carlo code, iii) evaluation of criticality accident and iv) modification of the critical assembly STACY for the experiments for validation of criticality safety control methodology. After the last ICNC2019, the project has the substantial progress in the modification of STACY which will start officially operation from May 2024 and the development of the Monte Carlo Code "Solomon" suitable for the criticality calculation for materials having spatially random distribution complies with the power spectrum. We present the whole picture of this research and development project and status of each technical topics in the session.
Sato, Tomonori; Hata, Kuniki; Kaji, Yoshiyuki; Ueno, Fumiyoshi; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; et al.
JAEA-Review 2021-001, 123 Pages, 2021/06
JAEA-Review-2021-001.pdf:10.33MB
In the implement of the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), there are many problems to be solved. Specially, the mitigation of the aging degradation by the corrosion of the structural materials is important to implement the decommissioning safely and continuously. However, there are limited data for the environmental factors of corrosion in 1F, and the condition of 1F is continuously changing. So, the literature data for the water radiolysis and the corrosion under irradiation are listed as the database of corrosion under irradiation in this report. And the new obtained radiolysis and corrosion data, which have not been reported in the literature and will be required in the decommissioning of 1F, are reported.
Terada, Hiroaki; Nagai, Haruyasu
Isotope News, (775), p.44 - 48, 2021/06
no abstracts in English
Takahashi, Tomoyuki*; Uchida, Shigeo*; Takeda, Seiji; Nakai, Kunihiro*
KURNS-EKR-11, p.97 - 102, 2021/03
This paper outlines the status of IAEA database compilation for migration parameters depending elements in a biosphere such as soil-to-plant transfer factor and bioconcentration factor of marine products, and the status of utilization of the database in dose evaluation of radioactive waste disposal in Japan. Additionally, in the case of applying a new database to the dose evaluation for future radioactive waste disposal in a specific area. We summarized the opinions of specialists and result of general discussion about future strategies to make a new database for their parameters, perspectives to be considered in it, issues, etc.
Saito, Hiroshi; Nozawa, Takashi; Takemiya, Hiroshi; Seki, Akiyuki; Matsubara, Takeshi; Saito, Kimiaki; Kitamura, Akihiro
JAEA-Review 2017-040, 34 Pages, 2018/03
JAEA-Review-2017-040.pdf:9.52MB
The accidents at Fukushima Daiichi Nuclear Power Station on March 11th 2011, released significant amount of radionuclide to the environment. It has migrated to the human habitation and raised concerns of possible effect on human health, and for that a lot of researches have been performed. JAEA created and opened "Database for Radioactive Substance Monitoring Data" for usage of obtained data. For accurate modelling and future forecast using numerical code and the data, "Supporting Environment for Processing Simulation Codes" has been operated. In addition, research results have been opened as Q&A style "Knowledge Base for Environmental Remediation" in JAEA's website. The "Comprehensive Evaluation System" composed of these components, should act more interrelated and integrated as one system. Besides, information dissemination is not enough to the outside. The report summarizes the current status, remaining issues and expected improvement of each component and the system.
Hamamoto, Takafumi*; Matsubara, Ryuta*; Shibutani, Sanae*; Suyama, Tadahiro*; Tachi, Yukio
JAEA-Data/Code 2017-014, 31 Pages, 2018/03
JAEA-Data-Code-2017-014.pdf:2.1MB
JAEA-Data-Code-2017-014-appendix(CD-ROM).zip:0.61MB
NUMO and JAEA have developed the methodology of post-closure safety assessment for the geological disposal. For this purpose, NUMO and JAEA have conducted a collaborative research project for developing the safety assessment methodology based on international state of the art knowledge. The present report focuses on investigation of sorption and diffusion data reported and their QA evaluation for updating sorption and diffusion database (SDB and DDB) as the collaborative research project between NUMO and JAEA. This report includes sorption and diffusion data for mainly sedimentary rocks and cement materials. As a result, 1,746 sorption data from 19 references and 593 diffusion data from 25 references were extracted and prepared in the datasheet of SDB and DDB.
setting approaches for rocks for the performance assessment of geological disposal; Application for granitic rocksTachi, Yukio; Suyama, Tadahiro*; Shibutani, Sanae*
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(2), p.109 - 133, 2017/12
For performance assessment (PA), the distribution coefficient (K) need to be determined taking into account the specific PA conditions, including geochemical variability or uncertainty. The K setting approach for rocks was developed by integrating three methods; (i) direct use of measured K data extracted from the sorption database, (ii) semi-quantitative estimation by scaling differences between experimental and PA conditions, and (iii) thermodynamic sorption models. This approach was tested for granitic rock by comparing K values and their uncertainties of Cs and Am. The results indicated that K can be quantitatively evaluated by all approaches when adequate data and models are available. The K dataset for safety-relevant 25 radionuclides was developed based on the direct use of measured data, and compared with the recent K dataset in European PA projects. This K setting approaches allowed to estimate the K values and their uncertainties under the expected site conditions.
Reactor Integral Test Working Group, JENDL Committee
JAEA-Data/Code 2017-006, 152 Pages, 2017/05
JAEA-Data-Code-2017-006.pdf:13.46MBJAEA-Data-Code-2017-006(errata).pdf:0.07MBJAEA-Data-Code-2017-006-appendix1(CD-ROM).zip:115.88MBJAEA-Data-Code-2017-006-appendix2(CD-ROM).zip:110.88MB
A benchmark database which is devoted to the evaluation of the future JENDL against the criticality of light water reactors was prepared, where the ICSBEP and IRPhEP handbooks by OECD/NEA were utilized effectively. Specific features of this report can be described as follows: (1) The recommendation for benchmarking is based on careful reviewing for the document and related information. Validity of the original benchmark evaluation is carefully checked, and numerical results obtained with JENDL-4.0 are considered. (2) Heterogeneity effect of PuO
particles dispersed in fuel medium is consistently quantified for the MOX fuel-loaded experimental data. This precise evaluation is realized by the newly developed finite fuel pin bundle model with the Monte Carlo neutron transport code. (3) Sensitivity analysis is conducted in order to specify nuclear data whose difference between recent nuclear data libraries significantly affects the critical parameter calculation.
Ikeda, Hiroshi; Kikuzawa, Nobuhiro; Yoshii, Akinobu*; Kato, Yuko
Proceedings of 13th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.637 - 640, 2016/11
no abstracts in English
Hayakawa, Misa; Yonezawa, Minoru; Mineo, Yukinobu; Kunii, Katsuhiko; Nagaya, Shun
Dai-12-Kai Joho Purofesshonaru Shimpojiumu (INFOPRO 2015) Happyo Yokoshu, p.129 - 134, 2015/12
no abstracts in English
Ikeda, Hiroshi; Kikuzawa, Nobuhiro; Yoshii, Akinobu*; Kato, Yuko
Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1312 - 1316, 2015/09
The Linac and the RCS in J-PARC provide enormous operation data and we have been stored them into PostgreSQL. We are planning to replace it with HBase, a data store specialized for big-data and is on a distributed file system provided by Hadoop, using a cluster with advantages including automatically recovering and easily extending the capacity. In the previous presentation we reported we updated HBase/Hadoop in our test system and we showed issues to fix our tools in the new system, while we also mentioned issues about the construction of our cluster itself. In this presentation we are reporting we have re-designed and re-constructed the cluster with resolving the issues, including enhancing hardware of master nodes, creating automatic scripts to construct nodes, and introducing monitoring tools for nodes. Having accordingly adjusted the configurations of HBase/Hadoop and measured the performance of our new system, we are also reporting its results and considerations.
Kurata, Masaki; Shirasu, Noriko; Kawakami, Kazuto*
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2015) (Internet), p.139 - 156, 2015/09
Thermodynamic database is a useful tool for evaluating preliminary chemical reactions during molten core concrete interaction and phase relations in fuel debris. Japan Atomic Energy Agency and Nippon Steel Sumitomo Metal Corporation are collaborating to develop an open thermodynamic database by combining their own nuclear- and steel/slag-databases. The phase diagrams of AlO
-UO, AlO-ZrO, SiO-UO, and UO-ZrO sub-systems and those of AlO-UO, SiO-UO, and AlO-ZrO sub-systems were able to be drawn properly using the cell model parameters and the sub-lattice model parameters assessed in the present study, respectively. The concerns for improving accuracy on the assessment were extracted in several sub-systems.
Sakai, Toshihiro; Matsuoka, Toshiyuki
JAEA-Research 2015-004, 109 Pages, 2015/06
JAEA-Research-2015-004.pdf:141.42MBJAEA-Research-2015-004-appendix(CD-ROM).zip:128.66MB
We update the geologic map and the database of the geological mapping published by Funaki et al. (2005a) and Ota et al. (2007) based on geological survey and topographical analysis data in and around the Horonobe area. There are many geological survey data which are derived from natural resources (petroleum, natural gas and coal, etc.) exploration in and around Horonobe-cho. We also use these data in addition to data in Funaki et al. (2005a) and Ota et al. (2007)'s data. As results of this report, we also construct a digital geologic map and a digital database of geological survey using GIS. These results can be expected to improve the precision of modeling and analyzing of geological environment, and its long-term evaluation.
Kikuzawa, Nobuhiro; Ikeda, Hiroshi; Yoshii, Akinobu*; Kato, Yuko; Ouchi, Nobuo
Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.794 - 798, 2014/10
no abstracts in English
Asami, Makoto; Watahiki, Hiromi; Oi, Takao; Makino, Hitoshi; Shibata, Atsuhiro; Kameo, Yutaka; Meguro, Yoshihiro; Ashida, Takashi
JAEA-Data/Code 2014-016, 37 Pages, 2014/09
JAEA-Data-Code-2014-016.pdf:37.04MBJAEA-Data-Code-2014-016-appendix(CD-ROM).zip:60.46MB
A database on the analyses of samples obtained from contaminated water in the circulating system of Fukushima Daiichi Nuclear Power Station was built. This database contains the analyses of 25 samples of JAEA and 313 samples of TEPCO which have been published in FY 2011 to FY 2013. Also, as well as the analyses on contaminated water, the information on the stored and treated amount in accumulated water and the amount of produced waste, which has been published by TEPCO and which might be required in order to estimate the inventory of secondary waste (sludge, used vessels) generated by treatment of contaminated water are contained in this database. This technical report shows the function of this database and user manual with example and presents the FY2013 edition of database by appendix CD.
Sasaki, Akira; Jo, Kazuki*; Kashiwagi, Hiroe*; Watanabe, Chiemi*; Suzuki, Manabu*; Lucas, P.*; Oishi, Masatoshi*; Kato, Daiji*; Kato, Masatoshi*; Kato, Takako*
Journal of Plasma and Fusion Research SERIES, Vol.7, p.348 - 351, 2006/00
no abstracts in English
Usuda, Shigekazu
Isotope News, (617), p.20 - 24, 2005/09
no abstracts in English
Sasaki, Akira; Murata, Masaki*; Kanamaru, Toshiyuki*; Shirado, Tamotsu*; Isahara, Hitoshi*; Ueshima, Yutaka; Yamagiwa, Mitsuru
Purazuma, Kaku Yugo Gakkai-Shi, 81(9), p.717 - 722, 2005/09
no abstracts in English
Sakamoto, Yoshiteru; Toi, Kazuo*; Fukuda, Takeshi*; Fukuyama, Atsushi*; Fujita, Takaaki; Ogawa, Yuichi*; Takizuka, Tomonori; Takenaga, Hidenobu; Yagi, Masatoshi*; Yamada, Hiroshi*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 81(8), p.626 - 627, 2005/08
no abstracts in English
Sako, Hiroyuki; Sakaki, Hironao; Takahashi, Hiroki; Yoshikawa, Hiroshi; Ito, Yuichi*; Kato, Yuko*; Kamikubota, Norihiko*; Sugimoto, Makoto*; Watanabe, Kazuhiko*; Ikeda, Hiroshi*; et al.
Proceedings of 2nd Annual Meeting of Particle Accelerator Society of Japan and 30th Linear Accelerator Meeting in Japan, p.462 - 464, 2005/07
Current status of the RDB system in J-PARC LINAC is presented. The machine database records static data of devices and the control system, whereas the operation log database records a history of operation parameters. The overall design of control flow among high-level applications, simulators, and database is described. Then results of a control test of the power supply for DTQ, and a prototype test of the operation log database in MEBT1 test bench at KEK are reported. In the end, a scheme to generate simulation configuration files from RDB is shown.
