Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2022

Kokubun, Yuji; Nakada, Akira; Seya, Natsumi; Nagaoka, Mika; Koike, Yuko; Kubota, Tomohiro; Hirao, Moe; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; et al.

JAEA-Review 2023-052, 118 Pages, 2024/03

JAEA-Review-2023-052.pdf:3.67MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2022. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2020

Nakano, Masanao; Nakada, Akira; Kanai, Katsuta; Nagaoka, Mika; Koike, Yuko; Yamada, Ryohei; Kubota, Tomohiro; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; et al.

JAEA-Review 2021-040, 118 Pages, 2021/12

JAEA-Review-2021-040.pdf:2.48MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2020. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2018

Nakano, Masanao; Fujii, Tomoko; Nagaoka, Mika; Inoue, Kazumi; Koike, Yuko; Yamada, Ryohei; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Kikuchi, Masaaki*; et al.

JAEA-Review 2019-045, 120 Pages, 2020/03

JAEA-Review-2019-045.pdf:2.54MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2018. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

Study on piping response under multiple excitation, 1; Triple shaking table test of piping having three-supporting points

Watakabe, Tomoyoshi; Kaneko, Naoaki*; Aida, Shigekazu*; Otani, Akihito*; Moriizumi, Makoto*; Tsukimori, Kazuyuki; Kitamura, Seiji

Proceedings of 2013 ASME Pressure Vessels and Piping Conference (PVP 2013) (DVD-ROM), 8 Pages, 2013/07

The piping in a nuclear power plant is laid across multiple floors of a single building or two buildings, which are supported at many points. As the piping is excited by multiple inputs from the supporting points during an earthquake, seismic response analysis by multiple excitations is needed to obtain the exact seismic response of the piping. However, few experiments involving such multiple excitations have been performed to verify the validity of multiple excitation analysis. To perform rational seismic design and evaluation, it is important to investigate the seismic response by multiple excitations and verify the validity of the analysis method by multiple excitation test. This paper reports on the result of the shaking test using triple uni-axial shaking tables and a 3-dimensional piping model.

Report of lower end plug welding, and test and inspection for the JOYO 6th refueling core fuel assembly

Kajiyama, Tadashi; Numata, Kazuaki; Otani, Seiji; *; *; Goto, Tatsuro*; Takahashi, Hideki*

JNC TN8440 2000-010, 45 Pages, 2000/02

JNC-TN8440-2000-010.pdf:1.45MB

This report describes about procedure and consequence of the welding process of the cladding tube and the lower end plug, the process of the test and inspection and the process of shipment for the 6th refueling core fuel assembly (46 fuel assemblies) of the experimental fast reactor JOYO. These works were carried out on July, 1996 from January, 1993 in Tamatukuri inspection branch of quality assurance section, technical administration division, plutonium fuel center. The 6th refueling core fuel assemblies are two kinds of the fuel assembly (1) and (2). The material of the lower end plug and the cladding tube used for the fuel assembly (1) is the type 316 stainless steel grade (here in after referred to as SUS316 grade) and austenitic stainless steel of high nickel content (here in after referred to as PNC 1520). That material used for the fuel assembly (2) is all SUS316 grade. The result of welding and the inspection is shown in the following table.

An investigation report on the defective occurrence of the lower end plug welded section for JOYO MK-III.; An investigation result about the inclusion occurrence

Kajiyama, Tadashi; Numata, Kazuaki; Otani, Seiji; Goto, Tatsuro*; Takahashi, Hideki*

JNC TN8430 2000-007, 44 Pages, 2000/02

JNC-TN8430-2000-007.pdf:5.32MB

Fabrication of the cladding tube with the lower end plug for the core fuel assembly of the experimental fast reactor JOYO and the proto-type fast breeder reactor MONJU has been performed by Tamatsukuri inspection branch of quality assurance section, Technical administration division, Plutonium fuel center since 1989. The fabrication process of the cladding tube with the lower end plug consists of numbering process of fuel element number to the lower end plug, welding process of the lower end plug and the cladding tube, and inspection process after welding (visual inspection, dimensional inspection and X-ray radiography). The processing of cladding tube with the lower end plug which is used for the initial loading core fuel assembly of JOYO MK-III has been carried out from August to May in 1996. The many tungsten inclusions were observed by X-ray radiography in the welds of the cladding tube with the lower end plug that were fabricated in the fourth fabrication campaign performed from July to August in 1996. The investigation of the causes was carried out about the welding process of the cladding tube and the lower end plug based on the fabrication record. The following three items were confirmed as a result. (1)As for the ingredients of inclusions observed by the X-ray radiography, it was proved by EPMA(Electron Probe X-ray Micro-analyzer) analysis that it was the same as the tungsten electrode. (2)Cracks, chips and consumption were observed in the tip of the electrodes used for welding of the lower end plug. And, cracks and chips were observed in the electrodes as well which hadn't been used. (3)It was proved that the tip of the electrode was exhausted remarkably when the distance between the tip of the electrode and the welding section became less than 0.08mm. (here in after to as the distance between the electrodes) Based on the above result, examination of reappearance for the inclusion generation was performed simulating the shape of cracks and chips ...

Comparison with limit analysis and primary stress in Tee

Kaneko, Naoaki*; Kitamura, Seiji; Jimbo, Noboru*; Mizutani, Takumi*; Otani, Akihito*

no journal, , 

no abstracts in English