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Chiba, Yusuke; Nishiyama, Yutaka; Tsubaki, Hirohiko; Iwai, Masaki
JAEA-Technology 2019-002, 29 Pages, 2019/03
JAEA-Technology-2019-002.pdf:2.43MB
Act on Special Measures Concerning Nuclear Emergency Preparedness was amended on the 30th of October in 2017. As the JAEA Emergency Assistance Organization, Maintenance and Operation Section for Remote Control Equipment in Naraha Center for Remote Control Technology Development started training for emergency response robots operation for operators in each site of JAEA in response to the new amendment. The training consists of three operations: small crawler-type mobile scouting robots, big crawler-type mobile robots with a manipulator or a long tong and small radio-controlled helicopters. The training has three classes (beginner, intermediate and advanced classes) depending on skills and experiences. This paper reports the training programs of emergency response robots operation of the beginner and intermediate classes which were used in the first half of fiscal 2018.
Kajitani, Yukio; ; Abe, Kazuyuki; Osaka, Masahiko; ; Hirosawa, Takashi; Koyama, Shinichi
PNC TN9440 97-004, 186 Pages, 1997/02
The 25th anniversary meeting of the Alpha-Gamma Facility (AGF) at O-arai Engineering Center of PNC was held on February 7. The AGF started to examine irradiated materials on october 1 and fuel pins irradiated in the Dounreay Fast Reactor, DFR332/2 on December 1, 1971. The contents in this paper of the anniversary meeting are as follows. (1)25 years history and challenging plan for 2000 year. (2)Maintenance logbook of the facility, apparatus and manipulators for 25 years. (3)Recent results of melting temperature, thermal conductivity and lattice constants in irradiated MOX fuels. (4)Development on fission products release measuring apparatus and results of cold run tests. (5)Post irradiated examination results operated at the metallography cell in the Fuels Monitoring Facility (FMF). (6)Development on chemical analysis method for minor actinides (MA) in irradiated MOX fuels. (7)Refurbishment for MA containing MOX fuels, status and specifications for the fabrication and quality control apparatus.
Kakehi, Isao; ; ; ; ; Kajitani, Yukio;
PNC TN9410 97-015, 382 Pages, 1996/12
For the purpose of developing the future nuclear fuel recycle system, the design study of the advanced nuclear fuel recycle system is being conducted. This report describes intermediate accomplishments in the conceptual system study of the advanced nuclear fuel recycle system. Fundamental concepts of this system is the recycle system using molten salt which intend to break through the conventional concepts of purex and pellet fuel system. Contents of studies in this period are as follows, (1)feasibility study of the process by Cd-cathode for nitride fuel (2)application study for the molten salt of low melting point (AlCl
+organic salt)(3)research for decladding (advantage of decladding by heat treatment)(4)behavior of FPs in electrorefinning (behavior of iodine and volatile FP chlorides, FPs behavior in chlorination) (5)criticaliy analysis in electrorefiner (6)drawing of off-gas flow diagram (7)drawing of process machinery concept (cathode processor, vibration packing) (8)evaluation for the amounts of the high level radioactive wastes (9)quality of the recycle fuels (FPs contamination of recycle fuel) (10)conceptual study of in-cell handling system (11)meaning of the advanced nuclear fuelrecycle system. The conceptual system study will be completed in describing concepts of the system and discussing issues for the developments.
Saito, Junichi; ; Jitsukawa, Shiro; ; Omi, Masao; Kizaki, Minoru
KAERI-NEMAC/TR-32/95, 0, p.210 - 219, 1995/00
no abstracts in English
Obara, Kenjiro; Nakamura, Kazuyuki; Murakami, Yoshio; *; *
Shinku, 31(5), p.342 - 346, 1988/05
no abstracts in English
; ; Murakami, Yoshio
Shinku, 28(5), p.351 - 353, 1985/00
no abstracts in English
Nakayama, Jiro; Sumi, Hirotaka; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji
no journal, ,
no abstracts in English
Shimazaki, Yosuke; Sawahata, Hiroaki; Yanagida, Yoshinori; Shinohara, Masanori; Kawamoto, Taiki; Takada, Shoji
no journal, ,
In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing 
Cf with 3.7GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source (NS) which is changed at the interval of approximately 7 years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. Technical issues were recognized for the transportation container in the past two exchange works for the safety handling work of NS holder. On the other hand, it was required that an overhaul of the conventional transportation container or development of a new transportation container because the conventional transportation container was manufactured about twenty years ago. Therefore, the development of a new transportation container for NSs, which can solve these technical issues with low cost, was carried out.
Shimazaki, Yosuke; Sawahata, Hiroaki; Yanagida, Yoshinori; Shinohara, Masanori; Kawamoto, Taiki; Takada, Shoji
no journal, ,
In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing Cf with 3.7 GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source (NS) which is changed at the interval of approximately 7 years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. Technical issues were recognized for the transportation container in the past two exchange works for the safety handling work of NS holder. On the other hand, it was required that an overhaul of the conventional transportation container or development of a new transportation container because the conventional transportation container was manufactured about twenty years ago. Therefore, the development of a new transportation container for NSs, which can solve these technical issues with low cost, was carried out. Radiation exposure dose of workers was reduced. As the result, it was confirmed that the NS handling work was improved by new transportation container.
