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Marufuji, Takato; Sato, Takumi; Ito, Hideaki; Suzuki, Hisashi; Fujishima, Tadatsune; Nakano, Tomoyuki
JAEA-Technology 2019-006, 22 Pages, 2019/05
Radioactive contamination incident occurred at Plutonium Fuel Research Facility (PFRF) in Oarai Research and Development Institute, Japan Atomic Energy Agency on June 6, 2017. During inspection work of storage container containing nuclear fuel materials, the PVC bag packaging in the storage container ruptured when a worker opened the lid in the hood, and a part of contents was spattered over the room. The cause of the increase of internal pressure of the storage container was gas generation by alpha radiolysis of the epoxy resin mixed with nuclear fuel materials. Opening inspection of about 70 similar containers stored in PFRF has been planned to confirm the condition of the contents and to stabilize the stored materials containing organic compounds. For safe and reliable open inspection of the storage containers with high internal pressure in the glove box, it is necessary to develop a pressure-resistant chamber in which the storage containers are opened and the contents are inspected under gastight condition. This report summarizes the concerns and countermeasures of the chamber design and the design results of the chamber.
Kaneko, Tetsuji; Tsukatani, Ichiro; Kiuchi, Kiyoshi
JAERI-Tech 2004-035, 18 Pages, 2004/03
Fuel elements used in the Reduced-Moderation Water Reactor (RMWR) have the stacking structure consisting of MOX pellets and UO blankets in a fuel rod in order to attain the high breeding ratio and high burn-up simultaneously. It is a characteristic of the fuel elements that there is high thermal stress caused by inhomogeneous linear power density along the longitudinal direction of the fuel rod in comparison with the present LWR fuels. For this reason, it is important to estimate local deformation behavior of the fuel cladding tube with temperature difference caused by MOX pellet and UO blanket. The testing machine was designed to investigate thermal-fatigue behavior under biaxial stress condition. The testing machine consists of the temperature distribution control unit, low cycle fatigue testing unit and internal pressure loading unit, it is also possible to conduct the simulation tests to investigate effects of pressure change with burn-up and longitudinal load change due to operation modes and restriction of fuel rods.
Sukegawa, Takenori; Hatakeyama, Mutsuo; Yanagihara, Satoshi
JAERI-Tech 2001-058, 81 Pages, 2001/09
In general, neutron transport and activation calculation codes are used for residual radioactive inventory estimation; however, it is essential to verify calculations by measurement results because of geometrical complexity of the reactor and so on. The comparison between measured and calculated radioactivity in the JPDR core components showed a relatively good agreement (factor of 2), and it was cleared that water content and weight ratio of steel bars to concrete materials significantly influenced the neutron flux distribution in the biological shield (factor of 2-10 error). The measured radioactivity inside of the reactor pressure vessel wall and at the inner part of the biological shield was compared in detail with the calculations to verify the methodology applied to calculations of radioisotope production. Then it was found that the radioactive inventory could be estimated accurately with combination of calculations and measurement of radioactivity in samples and dose rate distribution for planning of dismantling activities.
Sawa, Kazuhiro; Ueta, Shohei; Sumita, Junya; Tobita, Tsutomu*; Minato, Kazuo
Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 11 Pages, 2001/00
no abstracts in English
; Hoshi, Tatsuo; Tachibana, Mitsuo
Low and Intermediate Level Radioactive Waste Management,Vol. 1, p.189 - 195, 1991/00
no abstracts in English
Tachibana, Mitsuo; Hoshi, Tatsuo; Miki, Ichiro
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.81 - 84, 1991/00
no abstracts in English
Ozeki, Takahisa; Azumi, Masafumi
Journal of the Physical Society of Japan, 59(12), p.4338 - 4345, 1990/12
Times Cited Count:0 Percentile:0.01(Physics, Multidisciplinary)no abstracts in English
Ozeki, Takahisa; Azumi, Masafumi
JAERI-M 90-170, 23 Pages, 1990/10
no abstracts in English
Yanagihara, Satoshi; ; Nakamura, Hisashi
Nuclear Technology, 86, p.148 - 158, 1989/08
Times Cited Count:12 Percentile:77.45(Nuclear Science & Technology)no abstracts in English
Yanagisawa, Kazuaki; ; *
JAERI-M 89-055, 19 Pages, 1989/05
no abstracts in English
; Ueda, Shuzo
Int.J.Press.Vessels Piping, 30(1), p.37 - 56, 1987/01
Times Cited Count:1 Percentile:54.87(Engineering, Multidisciplinary)no abstracts in English
; ; ; ;
JAERI-M 9624, 56 Pages, 1981/08
no abstracts in English
; ; ; *
JAERI-M 6631, 18 Pages, 1976/07
no abstracts in English
; ; ;
JAERI-M 6249, 10 Pages, 1975/09
no abstracts in English