Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Collaborative Laboratories for Advanced Decommissioning Science; Hokkaido University*
JAEA-Review 2023-027, 126 Pages, 2024/03
JAEA-Review-2023-027.pdf:5.51MB
The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2022. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2020, this report summarizes the research results of the "Study on rational treatment/disposal of contaminated concrete waste considering leaching alteration" conducted from FY2020 to FY2022. The present study aims to understand migration behaviors of radionuclides in relation to the properties of concrete altered by leaching, to develop migration model of radionuclides, and to evaluate waste management scenarios, focusing on underground concrete structures in contact with contaminated water.
Collaborative Laboratories for Advanced Decommissioning Science; Hokkaido University*
JAEA-Review 2022-038, 102 Pages, 2023/01
JAEA-Review-2022-038.pdf:4.76MB
The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2021. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2020, this report summarizes the research results of the "Study on rational treatment/disposal of contaminated concrete waste considering leaching alteration" conducted in FY2021. The present study aims to understand migration behaviors of radionuclides in relation to the properties of concrete altered by leaching, to develop a model to predict concentration profiles, and to analyze waste management scenarios, with a focus on underground concrete structures in contact with contaminated water. Migration behaviors depend on radionuclides and their chemical species. Sorption of I
is less significant on C-S-H and C-A-S-H than on hardened cement paste with two orders of magnitude smaller distribution coefficient 
, while of U was the same …
I in the terrestrial environment after the Fukushima Dai-ichi Nuclear Power Plant accidentHonda, Maki
Chikyu Kagaku, 55(4), p.176 - 192, 2021/12
Iodine 129 (I) is a radionuclide that decays to Xe with a half-life of 15.7 million years. The analysis of I in the environment has played an important role not only in the fields of planetary science and earth science, but also in the nuclear field in recent years. Particularly, in the case of the Fukushima Dai-ichi Nuclear Power Plant accident in March, 2011, the scientists estimated the distribution and soil deposition of 
I over a wide area, and contributed to the assessment of internal exposure doses in the early stage of the accident. This is one of the most significant achievements in recent I-related studies. Future studies are expected to be conducted to elucidate the transport mechanism of I from land to river and sea, and to investigate the possible accumulation of I in aquatic organisms. The mobility of I in the soil studied by the author during the 10-years since the accident has been mainly reviewed in this manuscript.
Igarashi, Go*; Haga, Kazuko*; Yamada, Kazuo*; Aihara, Haruka; Shibata, Atsuhiro; Koma, Yoshikazu; Maruyama, Ippei*
Journal of Advanced Concrete Technology, 19(9), p.950 - 976, 2021/09
Times Cited Count：5 Percentile：38.2(Construction & Building Technology)Saito, Kimiaki; Mikami, Satoshi; Ando, Masaki; Matsuda, Norihiro; Kinase, Sakae; Tsuda, Shuichi; Sato, Tetsuro*; Seki, Akiyuki; Sanada, Yukihisa; Wainwright-Murakami, Haruko*; et al.
Journal of Radiation Protection and Research, 44(4), p.128 - 148, 2019/12
Shimada, Taro; Takubo, Kazuya*; Takeda, Seiji; Yamaguchi, Tetsuji
Progress in Nuclear Science and Technology (Internet), 5, p.183 - 187, 2018/11
After fuel debris is removed from the reactor containment vessel at Fukushima Daiichi NPS (1F) and collected in waste containers in the future, the waste containers will be disposed at a deep geological repository. The uranium inventory and uranium-235 (
U) enrichment of the fuel debris are larger than those of high-level vitrified wastes which are produced from liquid waste during reprocessing of spent nuclear fuels. Therefore, there is a possibility not to be excluded that a criticality occurs in the geological media where the uranium precipitates at the far-field from the repository, after the uranium located in the repository is dissolved by groundwater. In this study, we calculated the quantity of uranium precipitated at the natural barrier, and studied dimension of uranium deposited in the natural barrier and carried out the criticality analysis.
Miyahara, Kaname
Transactions of the American Nuclear Society, 117(1), p.51 - 52, 2017/10
This presentation highlights JAEA's challenges for contributing to recovering the previous life of residents and the development of resilient communities in Fukushima Prefecture based on considering needs of local people on the environmental restoration categorized by the state of evacuation orders and the lifting of such orders.
Kurikami, Hiroshi; Kitamura, Akihiro; Yamada, Susumu; Machida, Masahiko
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05
Several numerical models have been prepared to deal with various time- and spatial-scale issues related to radioactive cesium migration in environment in Fukushima area. This paper describes fragments of the JAEA's approaches of modeling to deal with the issues corresponding to radioactive cesium migration in environment with some case studies.
Matsunaga, Takeshi; Monte, L.; Tsuzuki, Katsunori; Yanase, Nobuyuki; Hanzawa, Yukiko; Ueno, Takashi
JAERI-Review 2003-039, 150 Pages, 2004/01
JAERI-Review-2003-039.pdf:11.12MB
Concerning radionuclides that might be released in an event of an accident from a nuclear facility, much attention has been paid to the migration pathways including the inflow to surface water bodies since the Chernobyl accident. In order to have discussions related to the current development of a mathematical model of the behavior of radionuclides in a river watershed, JAERI invited a guest scientist specializing in mathematical modeling of radioecology, Luigi Monte of Italian National Agency for New Technologies Energy and the Environment (ENEA: Ente per le Nuove tecnologie,L'Energia e l'Ambiente) of Italy, from May 22 to June 20 of 2003. This report is a summary of presentations and discussion made at the occasion of the visit of Dr. Monte at JAERI and also at relevant institutions of Japan involved in this study field. As a result of these discussions, distinct advantages and key problems of a mathematical model for prediction of the migration of radionuclides in a river watershed have been identified and analyzed.
Kobayashi, Takuya; Nagai, Haruyasu; Chino, Masamichi; Togawa, Orihiko
Proceedings of International Symposium on Radioecology and Environmental Dosimetry, p.500 - 504, 2003/00
The possibility of radionuclide release to the environment is on the increase due to a growth of nuclear facilities in Asia, military problems, nuclear terrorism, etc. The released radionuclides circulate among the atmospheric, oceanic and terrestrial environment, influencing human and natural environment through complex processes. In order to reduce the damage from these pollutants, it is necessary to estimate their migration behavior in detail. A software system SPEEDI-MP (SPEEDI Multi-model Package) is under development to resolve such environmental problems by simulating the 'inclusive and successive' behavior of pollutants in the atmospheric, oceanic and terrestrial environment. As code verification, the system has been applied to a hypothetical accident of a nuclear submarine if it sinks in an offshore region around Japan. The predicted results are examined, and the applicability and validity of the system are discussed.
Kumata, Masahiro; Nakayama, Shinichi; Vandergraaf, T. T.*; Drew, D. J.*
JAERI-Conf 99-004, p.395 - 410, 1999/03
no abstracts in English
Togawa, Orihiko
JAERI-Data/Code 95-009, 35 Pages, 1995/07
JAERI-Data-Code-95-009.pdf:1.43MB
no abstracts in English
*;
JAERI-M 86-063, 92 Pages, 1986/03
no abstracts in English
Oyama, Takuya; Ishikawa, Hiroyasu
no journal, ,
Iijima, Kazuki; Miyahara, Kaname
no journal, ,
This presentation provides a concise overview of knowledge and experience gained from the activities for environmental remediation after the Fukushima Daiichi (1F) accident to establish the technical basis for strategic, off-site response to nuclear incidents. It reflects JAEA's key role in the research associated with both remediation of contaminated areas and also the natural contamination migration processes in non-remediated areas. This presentation also provides a perspective on the future actions required to remediate all areas outside the 1F site, where continuing R&D is essential to facilitate return of residents to the most contaminated zones from the standpoint of environmental chemistry and radiochemistry with special emphasis on associated waste management.
Liu, J.; Dotsuta, Yuma; Kitagaki, Toru; Kozai, Naofumi; Yamaji, Keiko*; Onuki, Toshihiko
no journal, ,
Fuel debris was formed in severe accident in nuclear power plant. After the confirmation of microorganisms in water in damaged plant, it is necessary to consider the element migration of fuel debris. Here, some widespread bacteria were applied. By cultivation with simulant fuel debris, the migration mechanism was estimated.
Iijima, Kazuki; Fujiwara, Kenso; Matoba, Daisuke*; Sasaki, Takayuki*
no journal, ,
Depth profiles of radionuclides discharged to the environment of Fukushima was obtained in the forest soil just nearby the Fukushima Daiichi Nuclear Power Station (FDNPS). According to characteristics of the depth profile, Pu-238 was originated from the FDNPS accident, while Pu-239+240 was mainly originated from global fallout. Comparing depth profiles attributed by the accident and global fallout can give understanding on the migration behavior of Pu in subsurface soil during decades. In this study, advection-dispersion model was applied to evaluate the depth profiles of Pu isotopes. The Kd values for global fallout Pu-239+240 agreed with those of Fukushima Pu-238 within around factor 3. Therefore, migration behavior of Pu could be understood by the advection-dispersion model.
