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JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in radioactive waste generated from the dismantling of research reactors

Murakami, Masashi; Hoshino, Yuzuru; Nakatani, Takayoshi; Sugaya, Toshikatsu; Fukumura, Nobuo*; Sanda, Toshio*; Sakai, Akihiro

JAEA-Technology 2019-003, 50 Pages, 2019/06

JAEA-Technology-2019-003.pdf:4.42MB

Toward the establishment of a common approach to determine the radioactivity concentrations in dismantling wastes arising from research reactors, radionuclide concentrations in the reactor structure materials of aluminum, carbon steel, shield concrete, and graphite of TRIGA Mark II reactor at Rikkyo University, Japan, were evaluated with both radiochemical analysis and theoretical calculation. The measured nuclides by the radiochemical analysis were $$^{3}$$H, $$^{60}$$Co, and $$^{63}$$Ni in aluminum, $$^{3}$$H, $$^{60}$$Co, $$^{63}$$Ni, and $$^{152}$$Eu in carbon steel, $$^{3}$$H, $$^{60}$$Co, and $$^{152}$$Eu in shield concrete, and $$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{63}$$Ni, and $$^{152}$$Eu in graphite. Neutron-flux distributions and neutron-induced activities were computed with DORT and ORIGEN-ARP codes, respectively. Using the results of material composition analysis, radioactivity concentrations were conservatively predicted with good accuracy except for graphite material.

JAEA Reports

Study on the basic system of the common non-destructive radioactivity measuring equipment for disposal of radioactive wastes generated from research, industrial and medical facilities

Izumo, Sari; Hayashi, Hirokazu; Nakata, Hisakazu; Amazawa, Hiroya; Motoyama, Mitsushi*; Sakai, Akihiro

JAEA-Technology 2018-018, 39 Pages, 2019/03

JAEA-Technology-2018-018.pdf:2.8MB

JAEA has planed the near surface disposal of LLW generated from research, industrial, and medical facilities. Maximum radioactivity concentration of each waste and total radioactivity of disposed wastes are needed to be less than the permitted values in the license of disposal facility. Thus, it is important not to evaluate the radioactivity of each waste in unduly conservative ways so as to dispose of the total amount of the waste that is originally planned. Accordingly, the detection limit is required to be as low as the clearance level for the very low level radioactive waste planned to be disposed of trench-type. In this report, the feasibility of the non-destructive assay method is studied by model calculations for gamma emitters. It is confirmed that the detection limit less than the clearance level can be achieved as regards the box type metal container that is difficult to measure. This report summarizes the requirements for the non-destructive measuring equipment.

JAEA Reports

Study on the evaluation methodology of the radioactivity concentration in low-level radioactive wastes generated from JRR-2 & JRR-3

Hayashi, Hirokazu; Izumo, Sari; Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro

JAEA-Technology 2018-001, 66 Pages, 2018/06

JAEA-Technology-2018-001.pdf:4.12MB
JAEA-Technology-2018-001(errata).pdf:0.54MB

It is necessary to establish evaluation methodology of radioactivity concentrations of each radionuclide in waste packages for operation of the Near-surface Trench disposal and Sub-surface Pit disposal facility in near future, which has been preparing for low-level radioactive wastes generated from research facilities in JAEA. The radionuclides containing in waste packages generated from both JRR-2 and JRR-3, which are H-3, C-14, Cl-36, Co-60, Ni-63, Sr-90, Nb-94, Tc-99, Ag-108m, I-129, Cs-137, Eu-152, Eu-154, U-234, U-238, Pu-239+240, Pu-238+Am-241, Cm-243+244, were evaluated their density based on radiochemical analysis data, and the Evaluation Methodology of the Radioactivity Concentration such as Scaling Factor method and mean activity concentration method was studied in this report.

Journal Articles

Challenges for management of radioactively contaminated wastes and volume reduction and reuse/recycling of removed soil derived from the activities for environmental remediation after the Fukushima Daiichi Nuclear Power Station accident, 5; Cost evaluation method for the disposal of low level radioactive waste

Nakata, Hisakazu; Sakai, Akihiro; Amazawa, Hiroya; Sakamoto, Yoshiaki

Nippon Genshiryoku Gakkai-Shi, 59(8), p.447 - 449, 2017/08

Removed soil except those that may be reusable/recyclable would be finally disposed of. A general view is obtained in regards to a disposal concept of low level radioactive wastes generated from research, industrial and medical facilities, for the purpose of contributing to designing final disposal facilities of removed soil. It is analyzed to investigate the issues relating to cost evaluation in order to reasonably carry out that design, referring to a cost evaluation methodology applied to a trench-type disposal facility, which has been planned by JAEA, with impermeable layers.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in radioactive waste generated from post-irradiation examination facilities, 2

Tsuji, Tomoyuki; Hoshino, Yuzuru; Sakai, Akihiro; Sakamoto, Yoshiaki; Suzuki, Yasuo*; Machida, Hiroshi*

JAEA-Technology 2017-010, 75 Pages, 2017/06

JAEA-Technology-2017-010.pdf:2.31MB

It is necessary for reasonable disposal to be studied on evaluation methods to determine radioactivity concentrations in the radioactive wastes, which is generated from post-irradiation examination (PIE) facilities, for establishment of reasonable confirmation methods concerning radioactive wastes generated from research, industrial, and medical facilities. It has been chosen the PIE facilities of NUCLEAR DEVELOPMENT CORPORATION as a model for this study. As a result, it has been confirmed that the theoretical methods are applied for the important nuclides (H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-137, Eu-154, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Am-241 and Cm-244).

JAEA Reports

Waste Technical Standards Working Group annual report 2015

Waste Technical Standards Working Group

JAEA-Review 2016-020, 61 Pages, 2016/09

JAEA-Review-2016-020.pdf:1.55MB

Radioactive Waste Management and Disposal Project Department has set up a Working Group for the purpose of sharing information within the Sector of Decommissioning and Radioactive Wastes Management of Japan Atomic Energy Agency, heading towards implementation of disposal of low level radioactive waste generated from research, medical and industrial facilities. Waste package quantities and its radioactivity inventory which are needed for disposal project planning and facility design, as well as methods for corresponding to the technical standards on confirmation related to waste disposal, radioactivity evaluation techniques and quality control methods have been addressed in the Working Group. This annual report summarizes the activities of the Working Group in the FY 2015 regarding quality management system related to the manufacturing of the waste packages, standard manual for radioactivity data acquisition of JAEA and future issues on the basis of the results by 2014.

Journal Articles

The Verification tests of the melting conditions for homogenization of metallic LLW at the JAEA

Nakashio, Nobuyuki; Osugi, Takeshi; Iseda, Hirokatsu; Tohei, Toshio; Sudo, Tomoyuki; Ishikawa, Joji; Mitsuda, Motoyuki; Yokobori, Tomohiko; Kozawa, Kazushige; Momma, Toshiyuki; et al.

Journal of Nuclear Science and Technology, 53(1), p.139 - 145, 2016/01

 Times Cited Count:1 Percentile:83.2(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Chemical stability of solidified products made from incombustible wastes by plasma melting

Kameo, Yutaka; Haraga, Tomoko; Nakashio, Nobuyuki; Hoshi, Akiko; Nakashima, Mikio

Nippon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.354 - 362, 2004/12

In order to investigate chemical stability of solidified products made from Low Level Radioactive Wastes (LLW) by plasma melting, a leaching test based on the MCC (Material Characterization Center)-3S Agitated Powder Leach Test Method was performed to determine Normalized Elemental Mass Loss (NL$$_{i}$$) of both main components (Na, Al, Si, Ca, and Fe) of the solidified product and radioactive tracers ($$^{60}$$Co, $$^{137}$$Cs, and $$^{152}$$Eu) incorporated into it. The results of leaching test indicated that NLi value was greatly affected by basicity defined as weight ratio of CaO to SiO$$_{2}$$ in the solidified product, while effect of FeO concentration on NL$$_{i}$$ value was small. In the case of basicity less than 0.8, logarithm of NL$$_{i}$$ linearly increased with the basicity, implying that NL$$_{i}$$ value can be estimated by chemical composition of the solidified products.

Journal Articles

Characterization of solidified products yielded by plasma melting treatment of simulated non-metallic radioactive wastes

Nakashima, Mikio; Fukui, Toshiki*; Nakashio, Nobuyuki; Isobe, Motoyasu*; Otake, Atsushi*; Wakui, Takuji*; Hirabayashi, Takakuni*

Journal of Nuclear Science and Technology, 39(6), p.687 - 694, 2002/06

 Times Cited Count:12 Percentile:36.19(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JAEA Reports

Performance tests of a melting system for miscellaneous solid wastes and corrosion tests of a long-life refractory material (Contract research)

Isobe, Motoyasu; Kameo, Yutaka; Nakashio, Nobuyuki; Wakui, Takuji*; Iwata, Keiji*; Kibayashi, Tatsuyuki*; Kanazawa, Katsuo; Nakashima, Mikio; Hirabayashi, Takakuni*

JAERI-Tech 2000-049, 29 Pages, 2000/09

JAERI-Tech-2000-049.pdf:2.87MB

no abstracts in English

Journal Articles

An Opening in mortar produced from gas evolution of aluminium

Hashizume, Shuji*; Matsumoto, Junko; Bamba, Tsunetaka

Genshiryoku Bakkuendo Kenkyu, 6(1), p.101 - 106, 1999/12

no abstracts in English

JAEA Reports

Survey of the characteristics on the neogene sedimentary rocks in northern Kanto and northeast Japan along the pacific coast

Okuda, Katsuzo*; Takebe, Shinichi; Sakamoto, Yoshiaki; Hagiwara, Shigeru*; Ogawa, Hiromichi

JAERI-Review 99-023, p.100 - 0, 1999/10

JAERI-Review-99-023.pdf:4.63MB

no abstracts in English

Journal Articles

Application of laser to decontamination and decommissioning of nuclear facilities at JAERI

Hirabayashi, Takakuni; Kameo, Yutaka; Myodo, Masato

High-power Lasers in Civil Engineering and Architecture (Proceedings of SPIE Vol.3887), p.94 - 103, 1999/00

no abstracts in English

Journal Articles

Sorption behavior of organic carbon-14 onto cementitious materials

Matsumoto, Junko; Bamba, Tsunetaka

Proc. of 7th Int. Conf. on Radioactive Waste Management and Environmental Remediation (ICEM'99)(CD-ROM), 5 Pages, 1999/00

no abstracts in English

Journal Articles

Effect of direct contact with iron on gas evolution behavior of aluminum

Hashizume, Shuji; Matsumoto, Junko; Bamba, Tsunetaka

Genshiryoku Bakkuendo Kenkyu, 5(1), p.45 - 49, 1998/08

no abstracts in English

Journal Articles

Advanced volume reduction of low level radioactive solid waste

Hirabayashi, Takakuni

Energy Hum., 45, p.14 - 18, 1998/06

no abstracts in English

Journal Articles

Application of plasma-induction-hybrid melter to the research on volume reduction and stabilization of low level radioactive solid waste

Hirabayashi, Takakuni; Kanazawa, Katsuo; Fujiki, Kazuo; *; *

Proc. of Int. Conf. on Incineration & Thermal Treatment Technologies (IT3 Conference), p.261 - 264, 1998/00

no abstracts in English

Journal Articles

Effects of environmental factor on gas evolution behavior from Al in simulating mortar environments

Hashizume, Shuji; Matsumoto, Junko; Bamba, Tsunetaka

Zairyo To Kankyo, 47(10), p.638 - 644, 1998/00

no abstracts in English

JAEA Reports

42 (Records 1-20 displayed on this page)