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Radiation Risk Analysis Research Group, Risk Analysis and Applications Research Division
JAEA-Testing 2020-001, 65 Pages, 2020/03
JAEA-Testing-2020-001.pdf:4.42MB
The Nuclear Safety Research Center (NSRC) has developed a Level 3 Probabilistic Risk Assessment (PRA) code, the OSCAAR (Off-Site Consequence Analysis code for Atmospheric Release in Reactor Accident). Using a source-term derived from a severe accident analysis code, OSCAAR calculates the downwind transport, airborne dispersion, and ground deposition of radioactive materials as well as the radiation dose and then can evaluate the effect of early and late protective actions and health effect. The NSRC also developed the OSCAAR Code Package that has a Windows-based interface and framework for performing consequence analysis in order to create or modify input files, execute the OSCAAR and postprocess the output files efficiently and conveniently. The report is a user's manual for the OSCAAR Code Package.
Yonaga, Yusuke; Yoshikawa, Kiyotaka*; Shimada, Koji
JAEA-Testing 2020-002, 19 Pages, 2020/05
JAEA-Testing-2020-002.pdf:2.85MB
Rock thin sections are used for instrument analyses such as EPMA, LA-ICP-MS as well as microstructural observations by optical microscope. Fabrication of thin section, reported here, is one of the fundamental techniques in classical and state-of-the-art geological research. This report provides not only general procedure but also some ingenuity, precautions and equipment maintenance with visual exemplification for first-time or inexperienced users in the Tono Geoscience Center.
Sakashita, Koichi; Ishii, Naoyuki; Kijima, Jun; Aoyagi, Yoshitaka; Hagiwara, Masayoshi; Fukushima, Mineo
JAEA-Testing 2020-003, 20 Pages, 2020/07
JAEA-Testing-2020-003.pdf:1.52MB
Steam reforming method has been developed for the treatment of organic wastes which are not suitable materials (halogenated oil) for the incineration. This method consists of the gasification process in which organics are vaporized and decomposed with superheated steam and the oxidation process in which vaporized organics are decomposed by oxidizing reaction with heated air. In the gasification process, nonvolatile radionuclides are separated from vaporized waste. Therefore it can be expected that treatment of liquid waste generated from an off-gas treatment system and maintenance operation of the off-gas treatment system become easy to perform. 1,500L of waste oil contaminated with halogen, solvent and uranium was treated using the demonstration scale steam reforming system to examine the performance of the system in 2018. Results obtained this study were as follows; (1) The temperature in the steam reforming system was controlled under the self-regulation temperature. (2) The concentration of CO and NO
in the off-gas were controlled less than 100 ppm and 250 ppm respectively. (3) The gasification ratio of waste oil was more than 99%. (4) Concentration of fluorine oil in waste oil is needed to be less than 20wt% to perform stable continuance treatment.
Sugaya, Naoto; Okada, Yuji; Nishimura, Arashi; Sonobe, Hiroshi; Kimura, Nobuaki; Kimura, Akihiro; Hanawa, Yoshio; Nemoto, Hiroyoshi
JAEA-Testing 2020-004, 67 Pages, 2020/08
JAEA-Testing-2020-004.pdf:8.17MB
In the Japan Materials Testing Reactor (JMTR), the leakage accidents of radioactive waste liquid were occurred from the tanks and pipes of the liquid waste disposal facility in the JMTR tank-yard building in JFY2014. In order to respond to the accident, the tanks and pipes were replaced from JFY2016 to 2019. On the other hand, a lot of cracks were occurred on the concreate wall of the tank-yard building when the frame structure supports were fixed to the concrete wall in the replacement work. Thus, it is necessary to repair the concreate wall of the tank-yard building. Especially, some cracks with swelling (cone-shaped fracture) were raised around some anchor bolts (the post-installed chemical anchor bolts) fixed the frame structure supports. The repairing method for the cone-shaped fracture of the concrete wall is standardized, but there was no reference value of tensile strength for the validation of the post-installed chemical anchor bolts after the repairing method. In this report, the repairing method was selected for the cone-shaped fracture on the concreate wall and the reference value of tensile strength for the validation of the post-installed chemical anchor bolts by this repairing method. The mock-ups for repairing cone-shaped fracture were fabricated by the selected repairing method and the tensile tests of the post-installed chemical anchor bolts were performed. From the results, the validation of the repairing method was obtained in this test and it was obvious the repairing of cone-shaped fracture is preferable method for the concreate wall of the JMTR tank-yard building.
Chiba, Yusuke; Nishiyama, Yutaka; Tsubaki, Hirohiko; Iwai, Masaki; Furukawahara, Ryo; Ono, Hayato*; Hayasaka, Toshiro*
JAEA-Testing 2020-005, 29 Pages, 2021/02
JAEA-Testing-2020-005.pdf:3.07MB
Maintenance and Operation Section for Remote Control Equipment in Naraha Center for Remote Control Technology Development was the main part of the nuclear emergency response team of JAEA in full-scale operation starts on the 1st of April, 2020. In this section, we need to develop equipment for a JAEA nuclear emergency. To support full-scale operation, we have created a work robot for opening and closing doors, a work robot for opening and closing valves, and a reconnaissance robot for measuring radiation dose. This report describes how to operate the work robot (for opening and closing the door).
Chiba, Yusuke; Nishiyama, Yutaka; Tsubaki, Hirohiko; Iwai, Masaki; Ono, Hayato*; Hayasaka, Toshiro*
JAEA-Testing 2020-006, 24 Pages, 2021/02
JAEA-Testing-2020-006.pdf:3.35MB
Maintenance and Operation Section for Remote Control Equipment in Naraha Center for Remote Control Technology Development was the main part of the nuclear emergency response team of JAEA in full-scale operation starts on the 1st of April, 2020. In this section, we need to develop equipment for a JAEA nuclear emergency. To support full- scale operation, we have created a work robot for opening and closing doors, a work robot for opening and closing valves, and a reconnaissance robot for measuring radiation dose. This report describes how to operate a work robot (opening and closing valves).
Chiba, Yusuke; Nishiyama, Yutaka; Tsubaki, Hirohiko; Iwai, Masaki; Furukawahara, Ryo; Ono, Hayato*; Hayasaka, Toshiro*
JAEA-Testing 2020-007, 42 Pages, 2021/02
JAEA-Testing-2020-007.pdf:4.38MB
Maintenance and Operation Section for Remote Control Equipment in Naraha Center for Remote Control Technology Development was the main part of the nuclear emergency response team of JAEA in full-scale operation starts on the 1st of April, 2020. In this section, we need to develop equipment for a JAEA nuclear emergency. To support full-scale operation, we have created a work robot for opening and closing doors, a work robot for opening and closing valves, and a reconnaissance robot for measuring radiation dose. This report describes how to operate a Reconnaissance robot.
Magome, Hirokatsu; Iimura, Koichi; Matsui, Yoshinori
JAEA-Testing 2020-008, 52 Pages, 2021/02
JAEA-Testing-2020-008.pdf:5.46MB
As to the removal of the hydraulic rabbit No.1 irradiation facility related to the decommissioning of JMTR, points to be noted for considering a removal plan and maintenance methods after the removal were studied based on the past experiences of removing the hydraulic rabbit No.2 irradiation facility. As results, it became clear that it was necessary to (1) add a shutoff valve and a closing flange to piping for preventing cooling water leakage, (2) prepare a drawing jig for inner tube, and (3) shorten the remaining piping to withstand earthquakes. In addition, regarding the management of equipment to be maintained after removal, the necessary management items for the removal methods of the three patterns of ground equipments were listed.
Suzuki, Kenta; Abe, Fumiaki; Yashiro, Hiroshi; Kawabata, Kuniaki
JAEA-Testing 2020-009, 254 Pages, 2021/03
JAEA-Testing-2020-009.pdf:18.61MB
This report is the user manual of HAIROWorldPlugin for Choreonoid. Our motivation is to develop a robot simulator based on Choreonoid for technological development to contribute the decommissioning work at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings, Inc. Choreonoid is an open source simulator which calculates the behavior of robots. The plugin is an extended function of Choreonoid which provides simulated behavior and phenomenon related to decommissioning tasks utilizing remotely operated robots. In particular, we developed additional functionalities for simulating the behavior of an underwater swimming robot, the behavior of an unmanned aerial vehicle robot, low visibility camera images, network communication failures, etc., and packaged these in the plugin. This report describes the installation of the plugin to Choreonoid on Ubuntu18.04-LTS and parameter settings of the plugin by presenting snapshots of operation windows.
Kanno, Mizuho; Sueoka, Shigeru; Fukuda, Shoma
JAEA-Testing 2020-010, 38 Pages, 2021/03
JAEA-Testing-2020-010.pdf:3.07MB
This report provides procedures of He measurement for (U-Th)/He dating at Tono Geoscience Center, Japan Atomic Energy Agency. (U-Th)/He method is a radiometric dating based on alpha decay of U and Th series isotopes, being utilized as a thermochronometer. (U-Th)/He thermochronometries on zircon and apatite are especially useful to estimate thermal history at low temperatures. The procedures are presented with the details, tips, and cautions because parts of the procedures can be carried out by beginners, including students and contractors. This report also includes some document formats helpful for conducting the procedures.