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Journal Articles

Growing need for humanities and social science studies in uranium waste disposal

Yasuda, Hiroshi*; Fumoto, Hiromichi*; Saito, Tatsuo

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(8), p.610 - 614, 2021/08

Regarding the handling of uranium bearing waste, which is contaminated with uranium, which is a naturally occurring radionuclide, and its descendant nuclides, in recent years, the Japan Nuclear Regulatory Commission, etc. have been carefully and actively deliberated based on the knowledge of natural science and safety engineering. It was carried out, and as of March 2021, a certain policy has been shown. On the other hand, when disposing of uranium waste, which may cause dose exposure to future generations, the authors consider not only the science and engineering perspectives that have been conducted so far, but also the humanities and social science perspectives. We have been discussing with experts in related fields, thinking that it is necessary. In this report, we will introduce the background that brought about such an idea and the direction of future discussions.

Journal Articles

Activity report of the task group of radiation protection about wastes containing natural radioactive nuclides

Saito, Tatsuo; Kobayashi, Shinichi*; Zaitsu, Tomohisa*; Shimo, Michikuni*; Fumoto, Hiromichi*

Hoken Butsuri (Internet), 55(2), p.86 - 91, 2020/06

Safety cases for disposal of uranium bearing waste and NORM with uranium has not yet been fully developed in Japan, because of safety assessment of extraordinary long timespan and uncertainty in unexpected incidents with uncompleted radon impact evaluation measures arising from uranium waste disposal facility in far future. Our task group of radiation protection for wastes with natural radioactive nuclides studied some safety cases with disposal of uranium bearing waste and NORM in terms of nuclides, U-235, U-238 and their progenies, and comprehensively discussed the current state of their disposal in comparison to the ideas of international organizations such as ICRP and IAEA. We developed our ideas for long term uncertainty and radon with the knowledge of experts in each related area of direction, repeating discussions, focusing out the orientation of each directions, and outlined the recommendations with our suggestions of solving important issues in the future to be addressed.

JAEA Reports

Survey on uranium bearing waste disposal facilities in foreign countries

Saito, Tatsuo; Sakai, Akihiro; Sato, Kazuhiko; Yagi, Naoto; Hata, Haruhi; Fumoto, Hiromichi*; Kawagoshi, Hiroshi; Hasegawa, Makoto

JAEA-Review 2014-021, 30 Pages, 2014/07

JAEA-Review-2014-021.pdf:4.51MB

Japan Atomic Energy Agency surveyed the reference cases for the disposal of uranium bearing waste in low activity concentration as the contents of their own category 2 waste disposal facility for the Research and Development Activities. We reviewed the concepts mentioned in IAEA and ICRP documents, reference cases of uranium bearing waste disposal in selected countries (USA, Canada, UK, France and Sweden), and the disposal styles of long-lived radioactive waste were summarized, and the action items for application to the disposal system of our country was arranged. The disposal facilities in selected countries can be classified into 2 types with the length of performance assessment period for intruder scenario. They are long term assessment type and short term assessment type. It seems that the disposal system construction in category 2 waste disposal is the most realistic since there are many precedence examples of each country. Correspondence of 2 types of these disposal facilities is useful as a reference case.

JAEA Reports

Survey on uranium bearing waste disposal facilities in European countries

Sato, Kazuhiko; Sakai, Akihiro; Hata, Haruhi; Fumoto, Hiromichi*; Kawagoshi, Hiroshi; Saito, Tatsuo; Hasegawa, Makoto

JAEA-Review 2014-006, 78 Pages, 2014/03

JAEA-Review-2014-006.pdf:4.61MB

In this paper, we report the result of survey for basic principle of safety assessment for long-lived low-level (LL-LL) waste disposal and experience of the industrial waste disposal sites for uranium bearing waste in France, UK and Sweden, following the report of survey for U.S.A. and Canada published in December 2013.

JAEA Reports

Survey on uranium bearing waste disposal facilities in North American Continent

Hasegawa, Makoto; Saito, Tatsuo; Zaitsu, Tomohisa; Sato, Kazuhiko; Sakai, Akihiro; Fumoto, Hiromichi*

JAEA-Review 2013-043, 42 Pages, 2013/12

JAEA-Review-2013-043.pdf:4.24MB
JAEA-Review-2013-043-appendix(CD-ROM).zip:10.55MB

Uranium bearing waste in Japan is not included in Category-2 radioactive waste disposal in NSCRG: F-RW-I.02 (published in August 2010, NSC Japan). Therefore, disposal of uranium bearing waste should be considered in institutionalization. In charge of the consideration, it is thought effective to refer to the proven tactics of the uranium waste disposal in overseas and the information on a safe regulatory system. Since the view of regulations and enterprises in this field are progressing day by day, renewal of the existing information of disposal of the uranium waste in each country is required. Furthermore, amendment of the U.S. federal rule aiming at safety disposal of depleted uranium is in progress. It is important to collect and arrange the latest information on the two above-mentioned points. Therefore, it visited the disposal responsible organization and regulatory agency of the disposal site of the uranium waste in the U.S. and Canada, and held institution investigations and interviews paying attention to the following four items: (1) "amendment of the U.S. 10CFR61", (2) "Safety evaluation of uranium bearing waste", (3) "Disposal site design", (4) "Stakeholder involvement".

JAEA Reports

Study of assessing aqueous reprocessing process for the pipeless reprocessing plant -II

*; *; *; Fumoto, Hiromichi*; *; *

JNC TJ9400 2001-005, 128 Pages, 2001/03

JNC-TJ9400-2001-005.pdf:3.81MB

The purpose of this study is to investigate the possibility of adopting new reprocessing process by introducing pipeless plant concept, combined with aqueous separation methods other than solvent extraction method to be adopted to develop more economical FBR fuel (MOX fuel) reprocessing process. In this year, the following studies were made with technical view of interest for the purpose of evaluating the feasibility of the pipeless reprocessing plant adopting crystallization method and peroxide precipitation method, which are featured to be suitable to batch process, through the investigation in last year. (1)Process flow optimization for crystallization method and peroxide precipitation method (2)Material balance analysis and major equipment designing (3)Conceptual study on the pipeless plant adopting crystallization method and peroxide precipitation method (4)Construction cost evaluation of the pipeless plant adopting crystallization method and peroxide precipitation method (5)Extracting task to be solved and their possible way of solutions

JAEA Reports

Study of assessing aqueous reprocessing process for the pipeless reprocessing plant

*; *; Fumoto, Hiromichi*; *; *

JNC TJ9400 2000-001, 112 Pages, 2000/02

JNC-TJ9400-2000-001.pdf:6.67MB

The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1)The process adopting crystallization method and peroxide precipitation method (2)The process adopting oxalate precipitation method (3)The process under mild aqueous conditions (crystallization method and precipitation method) (4)The process adopting crystallization method and ion-exchange method (5)The process adopting crystallization method and solvent extraction method The processes (1)$$sim$$(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1)The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process.

JAEA Reports

None

*; Fumoto, Hiromichi*; *

JNC TJ6410 99-001, 57 Pages, 1999/03

JNC-TJ6410-99-001.pdf:3.15MB

Oral presentation

Progress report of the expert panel on management of NORM-containing wastes investigated through the perspective of humanities and social sciences

Yasuda, Hiroshi*; Saito, Tatsuo; Fumoto, Hiromichi*; Kasai, Atsushi*; Shimo, Michikuni*; Sugawara, Shinetsu*; Tsuchida, Shoji*; Furuta, Sadaaki*

no journal, , 

Contaminated with naturally occurring radionuclides uranium and its progeny nuclides, "uranium bearing wastes" have very long half-life to decay its radioactivity, which can be hundreds of thousands of years, and have risk to impose a considerable burden on future generations. Based on this, the authors considered that it is important to consider not only from the viewpoint of science and engineering as has been done so far, but also from the viewpoint of humanities and social sciences such as philosophy and history. Therefore, in 2020, the Health Physics Society of Japan established the "the Expert Panel on Management of NORM-Containing Wastes Investigated through the Perspective of Humanities and Social Sciences, and related fields". In this session, we will report on the history and future outlook of our activities so far.

Oral presentation

Activity report of the Task Group on Humanities and Social Sciences Perspectives on the Management and Disposal of Radioactive Waste

Yasuda, Hiroshi*; Fumoto, Hiromichi*; Saito, Tatsuo

no journal, , 

This project aims to discuss whether the approach of presenting exposure of future generations to radionuclides with long half-lives as potential exposure is compatible with the current concept of geological disposal, by extending the target from uranium waste to radioactive waste including intermediate and high level radioactive waste. The issues and the matters that should be presented and provided to the concerned parties, including future generations, are to be discussed extensively. The discussion will then organize ideas concerning issues such as how much concentration of waste can be disposed of, at what depth and scale, and what will be required when it is lost in the future, and will incorporate not only the science and engineering approach, but also the humanities and social science approach that the proponents have been considering, in order to provide a broader The proposers will discuss from a broader perspective, incorporating not only the science and engineering approach but also the humanities and social science approach that they have been considering. The status of these activities will be explained.

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