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Journal Articles

Dose estimation for contaminated soil storage in living environment

Takai, Shizuka; Shimada, Asako; Sawaguchi, Takuma; Takeda, Seiji; Kimura, Hideo

Radiation Protection Dosimetry, 188(1), p.1 - 7, 2020/01

 Times Cited Count:0 Percentile:0.01(Environmental Sciences)

After the Fukushima Nuclear Power Plant accident, most of radiocesium-contaminated soil generated from decontamination activities outside Fukushima prefecture has been stored at decontamination sites such as schools, parks and residential lands (storage at sites) according to the Decontamination Guidelines. However, additional exposure due to the present storage has not been evaluated. Moreover, entering storage sites, which is not restricted for storage at sites, was not considered in safety assessment conducted in the guidelines. To continue the storage and confirm the effectiveness, understanding of present possible exposures is important. In this study, we evaluated exposure doses for residents and users of storage sites based on the present situation. As a result, annual doses due to residence were 10$$^{-2}$$ to 10$$^{-3}$$ mSv y$$^{-1}$$ and doses due to annual entries were of the order of 10$$^{-3}$$ mSv y$$^{-1}$$. Hence, we confirmed that the exposure due to present storage outside Fukushima is significantly less than 1 mSv y$$^{-1}$$.

JAEA Reports

Rearrangement works of unbalanced waste packages by influence of the Great East Japan Earthquake

Ishihara, Keisuke; Kanazawa, Shingo; Kozawa, Masachiyo; Mori, Masakazu; Kawahara, Takahiro

JAEA-Technology 2017-002, 27 Pages, 2017/03

JAEA-Technology-2017-002.pdf:21.88MB

At radioactive waste management facilities in the Nuclear Science Research Institute, solid radioactive wastes are stored by using containers such as 200L drums and pallets to tier containers in 2 to 4 stacks in the height direction in waste storage facilities (Waste Storage Facility No.1, Waste Storage Facility No.2 and Waste Size Reduction and Storage Facility). On March 11, 2011, the Great East Japan Earthquake was happened, and some waste packages dropped from their pallets and large number of waste packages moved from their original position and inclined due to the influence of the earthquake in the waste storage facilities. There was no experience of rearrangement works to set those dropped and unbalanced waste packages in their original position and it was necessary to prepare detailed work procedures and progress for this task to prevent the occurrence of industrial accidents. Therefore, we prepared detailed work manual and repeatedly carried out mock-up test. And then, we started rearrangement work from April 2011 after confirmation of workers skill and adequacy of the work manual. Finally, all rearrangement works for stored waste packages took about four and half years and were completed in September 2015 without any accident and shutdown of storage function. This report summarizes the countermeasures to reduce exposure doses of workers and to prevent the occurrence of industrial accidents during the rearrangement works.

Journal Articles

Technical/institutional prerequisite for nuclear forensics response framework

Tamai, Hiroshi; Okubo, Ayako; Kimura, Yoshiki; Kokaji, Lisa; Shinohara, Nobuo; Tomikawa, Hirofumi

Dai-37-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu (CD-ROM), 8 Pages, 2017/02

Nuclear Forensics capability has been developed under the international collaborations. For its effective function, technical development in analysis of seized nuclear materials as well as the institutional development in comprehensive response framework are required under individual national responsibility. In order to keep the "chain of custody" in the proper operation of sample collection at the event scene, radiological analysis at the laboratory, storage of the samples, and further inspection and trial, close cooperation and information sharing between relevant organisations are essential. IAEA issues the Implementing Guide to provide the model action plan and assists individual national development. International cooperation for the technical improvement and awareness cultivation is promoted. Examples in such national developments will be introduced and prospective technical/institutional prerequisite for nuclear forensics response framework will be studied.

Journal Articles

Present status of MLF building layout and ancillary facilities

Kaminaga, Masanori; Haga, Katsuhiro; Kinoshita, Hidetaka; Torii, Yoshikatsu; Hino, Ryutaro; Ikeda, Yujiro

Proceedings of ICANS-XVI, Volume 1, p.125 - 133, 2003/07

no abstracts in English

Journal Articles

A Long-term maintenance plan for the JT-60 power supply

Omori, Yoshikazu; Matsukawa, Makoto; Omori, Shunzo; Terakado, Tsunehisa; Okano, Jun; Noda, Masaaki*

NIFS-MEMO-36, p.358 - 361, 2002/06

no abstracts in English

JAEA Reports

Conceptual design of the handling and storage system of the spent target vessel for a MW-class neutron scattering facility

Adachi, Junichi*; Kaminaga, Masanori; Sasaki, Shinobu; Hino, Ryutaro

JAERI-Tech 2000-068, 86 Pages, 2000/11

JAERI-Tech-2000-068.pdf:4.39MB

no abstracts in English

Journal Articles

Design study of handling and storage system of spent target for neutron scattering facility

Adachi, Junichi*; Sasaki, Shinobu; Kaminaga, Masanori; Hino, Ryutaro

FAPIG, (155), p.48 - 54, 2000/07

no abstracts in English

JAEA Reports

None

Fujita, Reiko*; *; Kondo, Naruhito*; Utsunomiya, Kazuhiro*

JNC TJ8420 2000-004, 41 Pages, 2000/03

JNC-TJ8420-2000-004.pdf:5.08MB

no abstracts in English

JAEA Reports

Physico-chemical studies on the disposal of miscellaneous radioactive waste through A single-step process (III)

Iwase, Masanori*

JNC TJ8400 2000-063, 78 Pages, 2000/03

JNC-TJ8400-2000-063.pdf:1.93MB

This study is aimed at controlling oxidation reaction of molten metal by ash in incineration systems, and at positively utilizing the oxidation reaction for decontamination of slag. In this year, in order to investigate physico-chemical properties of mixed fused salt containing alkali sulfates, with special focus on the behaviour of oxygen anion in the melts, Cu$$^{2+}$$ / Cu$$^{+}$$ redox equilibrium experiments were carried out. Among the effect of various parameters on Cu$$^{2+}$$ / Cu$$^{+}$$ ratio in binary and ternary alkali sulfate melts, the effect of partial pressures of oxygen and SO$$_{2}$$ was mainly investigated in the study. Variation in Cu$$^{2+}$$ / Cu$$^{+}$$ ratio were presented as the function of partial pressures of oxygen and SO$$_{2}$$, respectively. Possible thermodynamic interpretation were made on the experimental results. In addition, the dissolution of Cr$$_{2}$$O$$_{3}$$ in mixed alkali sulfates were also investigated as a first step to elucidate the mechanism of hot corrosion. With this investigation, an important finding was obtained that the solubility of Cr$$_{2}$$O$$_{3}$$ for melts with same average ionic radius, in other words, oxygen ion activity, were essentially identical under constant temperature and atmosphere.

JAEA Reports

None

Miyo, Hiroaki; ; Kudo, Kenji; Sukegawa, Yasuhiro*

JNC TN8440 99-005, 864 Pages, 1999/03

JNC-TN8440-99-005.pdf:40.45MB

None

Journal Articles

Decommissioning of the JRR-2

Kaieda, Keisuke; ; Arigane, Kenji

Genshiryoku Nenkan '98/'99-Nen Ban, P. 216, 1998/12

no abstracts in English

JAEA Reports

Safety research in nuclear fuel cycle at PNC

PNC TN1410 98-018, 69 Pages, 1998/09

PNC-TN1410-98-018.pdf:2.0MB

This report collects the results of safety research in nuclear fuel cycle at power reactor ans nuclear fuel development corporation, in order to answer to the questionnaire of OECD/NEA. The questionnaire request to inelude information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: (1) Recently completed reseach projects (2) Ongoing (current) research projects achievements on following items are omitted by request of oecd/nea. Uranium mining and milling, uranium refining and conversion to UF$$_{6}$$, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning we select topics from the fields of a (1) Nuclear installation, (2) Seismic, and (3) PSA, in projects from frame of annual safety research plan for nuclear installations established by nuclear safety ...

JAEA Reports

None

; ; ; ; ; ;

PNC TN8440 98-025, 111 Pages, 1998/07

PNC-TN8440-98-025.pdf:11.06MB

None

Journal Articles

Decommissioning of the nuclear ship Mutsu

Nihon Bunseki Senta Koho, 0(28), p.2 - 15, 1996/01

no abstracts in English

Journal Articles

The major part of the decommissioning work of the nuclear ship MUTSU completed

Kowan, 72(812), 42 Pages, 1995/08

no abstracts in English

JAEA Reports

None

Okada, Toshio; *; *; *; *; Miyake, Osamu; Sasaki, Shuichi

PNC TN1410 94-006, 57 Pages, 1994/11

PNC-TN1410-94-006.pdf:10.29MB

no abstracts in English

Journal Articles

Actual management of the JPDR Decommissioning Wastes

Yasunaka, Hideo; ;

Dekomisshoningu Giho, (6), p.50 - 60, 1992/11

no abstracts in English

JAEA Reports

High radioactive $$alpha$$-$$gamma$$ solid Waste treatment facilities Conceptual design study

*; Seki, Sadao*; *

PNC TJ9409 91-001, 164 Pages, 1991/02

PNC-TJ9409-91-001.pdf:4.41MB

This report describes the result of conceptual design study concerned with "High Radioactive $$alpha$$-$$gamma$$ Solid Waste Treatment Facilities, "which will be planed for the purpose of volume reduction and stabilization of High Radioactive $$alpha$$-$$gamma$$ solid wastes generated and stocked in the O-arai Engineering Center of PNC. In this conceptual design study the basic process of the facilities, which are sufficient to treat each waste and develop technologies, are clarified. This report consist with: (1)Clarification of waste to be treated. (2)Study on the treatment technology and process. (3)Conceptual design of facilities and equipment. (4)Estimation of construction cost and schedule.

Journal Articles

Treatment,storage and disposal technology for the decommissioned wastes

;

Genshiryoku Kogyo, 29(6), p.34 - 36, 1983/00

no abstracts in English

35 (Records 1-20 displayed on this page)