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JAEA Reports

Safe, efficient cementation of challenging radioactive wastes using alkali activated materials with high-flowability and high-anion retention capacity (Contract research); FY2019 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Hokkaido University*

JAEA-Review 2020-054, 72 Pages, 2021/01

JAEA-Review-2020-054.pdf:5.62MB

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 FY2019. 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 FY2019, this report summarizes the research results of the "Safe, efficient cementation of challenging radioactive wastes using alkali activated materials with high-flowability and high-anion retention capacity". The purpose of this study is to find safe, efficient cementation of challenging radioactive wastes using alkali activated materials with high-flowability and high-anion retention capacity, and to propose the concept of a manufacturing apparatus that is established as an actual plant. As a result of study in this year, it was revealed that the K-based alkali activated material has high-flowability and quick curing, and that high-iodine retention capacity is achieved by incorporating silver ions during manufacturing of solidified waste.

Journal Articles

Rapid dissolution techniques with microwave heating devices for solidified products made from non-metallic wastes by plasma melting

Haraga, Tomoko; Kameo, Yutaka; Nakashima, Mikio

Bunseki Kagaku, 55(1), p.51 - 54, 2006/01

 Times Cited Count:4 Percentile:14.45(Chemistry, Analytical)

A relatively large quantity of sample solutions have to be prepared for radiochemical analysis of solidified products yielded by plasma melting treatment of non-metallic radioactive wastes. In order to dissolve the solidified products sample rapidly, dissolution method with microwave heating devices was applied. In a conventional method only by external heating with various mixtures of acids (HNO$$_{3}$$, HF, HClO$$_{4}$$ and H$$_{2}$$SO$$_{4}$$), a 0.1 g amount of the sample was dissolved with difficulty. However, applying the microwave assisted dissolution method, a 1 g amount of the sample was completely dissolved in a shorter time. Thereby the time for dissolution procedures was shortened less than a one-tenth. The present dissolution method was successfully applied to the blast furnace slag as a reference material to determine main elements with good precision.

JAEA Reports

Study on coincidence and anti-coincidence $$gamma$$-ray spectrometry for the rapid radioactivity evaluation of solidified products prepared from radioactive wastes

Haraga, Tomoko; Kameo, Yutaka; Hoshi, Akiko; Yonezawa, Chushiro*; Nakashima, Mikio

JAERI-Tech 2005-050, 35 Pages, 2005/09

JAERI-Tech-2005-050.pdf:1.35MB

Non-destructive $$gamma$$-ray spectrometry has been examined as a simple and rapid radioactivity measurement technique for the solidified products prepared by plasma melting for low level radioactive miscellaneous wastes generated from nuclear facilities. The Compton background resulting from the coexisting radionuclides pose a problem in the usual $$gamma$$-ray spectrometry which uses only a Ge detector. In order to reduce the background count and to measure the interested nuclide selectively, the coincidence and the anti-coincidence $$gamma$$-ray spectrometry using the Ge-BGO detector system were examined. As a result of applying the anti-coincidence $$gamma$$-ray spectrometry to a single $$gamma$$-ray emitter $$^{137}$$Cs and the coincidence $$gamma$$-ray spectrometry to multiple $$gamma$$-ray emitter $$^{152}$$Eu under existence of $$^{60}$$Co, the detection limits of $$^{137}$$Cs and $$^{152}$$Eu in the sample, which contained $$^{60}$$Co, were reduced by a factor of about 6 and 1.5, respectively. It was confirmed that the present methods are useful for the $$gamma$$-activity measurement of solidified products.

JAEA Reports

Research on treatment and disposal of RI and research institute waste; Progress in Department of Fuel Cycle Safety Research

Department of Fuel Cycle Safety Research

JAERI-Review 2001-019, 108 Pages, 2001/07

JAERI-Review-2001-019.pdf:6.04MB

Department of Fuel Cycle Safety Research, JAERI, has been carrying out research on safe and rational disposal systems of radioactive wastes arising from medical activities and research institutes (RI and Research Institute Waste). The research area includes a study on molten solidified waste form, a geological survey on Japan, a proposal on integrated disposal systems, data acquisition for safety evaluation, and a safety analysis of disposal systems. This report introduces progress and future works for the treatment and disposal of RI and Research Institute Waste.

JAEA Reports

Melting behavior of low-level radioactive miscellaneous solid waste and characteristics of solidified products (Contract research)

Nakashio, Nobuyuki; Isobe, Motoyasu; Wakui, Takuji*; Iwata, Keiji*; Kibayashi, Tatsuyuki*; Kanazawa, Katsuo; Fukui, Toshiki; Otake, Atsushi*; Nakashima, Mikio; Hirabayashi, Takakuni*

JAERI-Research 2001-001, 19 Pages, 2001/02

JAERI-Research-2001-001.pdf:1.29MB

no abstracts in English

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