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JAEA Reports

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.

Journal Articles

Fabrication process qualification of TF Insert Coil using real ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200804_1 - 4200804_4, 2015/06

 Times Cited Count:0 Percentile:0(Engineering, Electrical & Electronic)

Journal Articles

Sensitivity analysis for the scenarios on deterioration or loss of safety functions expected in disposal system due to human error on application of engineering technology

Takeda, Seiji; Inoue, Yoshihisa; Kimura, Hideo

Materials Research Society Symposium Proceedings, Vol.1518, p.237 - 242, 2013/10

The sensitive analysis of radionuclide migration for the scenarios on deterioration or loss of safety functions expected in HLW disposal system due to the human error (initial defective scenarios) is performed in this study. Release rates for Cs-135 and Se-79 are estimated from Monte Carlo-based analysis. Maximum release rates of radionuclides for initial defective scenarios, buffer (colloidal transport case) and sealing plugs (pathway of short-circuit), are about one or two order magnitude higher than that normal scenario. From a viewpoint of future safety review, these results especially indicate the need to understand the feasibility on two types of initial defective scenario for the buffer and sealing plugs, leading to the loss of restraint of colloidal migration in the buffer and the loss of restraint with the plugs from migration through dominant pathway in tunnels and their vicinity.

Journal Articles

Compact DEMO, SlimCS; Design progress and issues

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.

Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07

 Times Cited Count:131 Percentile:98.1(Physics, Fluids & Plasmas)

Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m$$^{2}$$ or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).

JAEA Reports

Conceptual design and related R&D on ITER mechanical based primary pumping system

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya; Shimizu, Katsusuke*; Inoue, Masahiko*; Watanabe, Mitsunori*; Iguchi, Masashi*; Sugimoto, Tomoko*; Inohara, Takashi*; Nakamura, Junichi*

JAEA-Technology 2008-076, 99 Pages, 2008/12

JAEA-Technology-2008-076.pdf:35.19MB

The primary vacuum pumping system of the International Thermonuclear Experimental Reactor (ITER) exhausts a helium (He) ash resulting from the DT-burn with excess DT fueling gas, as well as performing a variety of functions such as pump-down, leak testing and wall conditioning. A mechanical based vacuum pumping system has some merits of a continuous pumping, a much lower tritium inventory, a lower operational cost and easy maintenance, comparing with a cryopump system, although demerits of an indispensable magnetic shield and insufficient performance for hydrogen (H$$_{2}$$) pumping are well recognized. To overcome the demerits, we newly fabricated and tested a helical grooved pump (HGP) unit suitable for H$$_{2}$$ pumping at the ITER divertor pressure of 0.1-10 Pa. Through this R&D, we successfully established many design and manufacturing databases of large HGP units for the lightweight gas pumping. Based on the databases, we conceptually designed the ITER vacuum pumping system mainly comprising the HGP with an optimal pump unit layout and a magnetic shield. We also designed conceptually the reduced cost (RC)-ITER pumping system, where a compound molecular pump combining turbine bladed rotors and helical grooved ones was mainly used. The ITER mechanical based primary pumping system proposed has eventually been a back-up solution, whereas a cryopump based one was formally selected to the ITER for construction.

Journal Articles

Ion irradiation effects on amorphization and thermal crystallization in Zr-Al-Ni-Cu alloys

Nagata, Shinji*; Higashi, Seijiro*; Tsuchiya, Bun*; To, Kentaro*; Shikama, Tatsuo*; Takahiro, Katsumi*; Ozaki, Koichi*; Kawatsura, Kiyoshi*; Yamamoto, Shunya; Inoue, Aichi

Nuclear Instruments and Methods in Physics Research B, 257(1-2), p.420 - 423, 2007/04

 Times Cited Count:16 Percentile:74.17(Instruments & Instrumentation)

Structural modification and primary precipitates in the Zr$$_{55}$$Al$$_{10}$$Ni$$_{5}$$Cu$$_{30}$$ alloy films (50-100 $$mu$$m thickness) caused by radiation with 300-500 keV H, Ag, Cu and Au ions has been studied. The results of XRD indicated that a metastable primary phase was formed in the alloy by the heat treatment after ion irradiation, but no difference was observed just after the ion irradiation at room temperature. Furthermore, higher incident Au ion fluence effectively suppressed thermal precipitation of the Zr$$_{2}$$Ni type crystalline phase in the alloy. The deposited energy dependence of the precipitation behavior indicated an increase of the nucleation sites by the implanted metal atoms, simultaneously with a decrease of the growth rate by higher energy deposition density.

Journal Articles

Development of elevated temperature structural design standard and three-dimensional seismic isolation technology for advanced nuclear power plant

Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Takahashi, Kenji; Ikutama, Shinya*; Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Kitamura, Seiji

Nihon Genshiryoku Gakkai-Shi, 48(5), p.333 - 338, 2006/05

no abstracts in English

Journal Articles

Surface wave on high speed liquid lithium flow for IFMIF

Kondo, Hiroo*; Fujisato, Atsushi*; Yamaoka, Nobuo*; Inoue, Shoji*; Miyamoto, Seiji*; Iida, Toshiyuki*; Nakamura, Hiroo; Ida, Mizuho*; Matsushita, Izuru*; Muroga, Takeo*; et al.

Fusion Engineering and Design, 75-79, p.865 - 869, 2005/11

 Times Cited Count:21 Percentile:80.43(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study on three-dimensional seismic isolation structure

Morishita, Maaki; Kitamura, Seiji; Takahashi, Kenji; Inoue, Kazuhiko*; Kato, Asao*; Fushimi, Minoru*

JNC TY9400 2005-010, 1150 Pages, 2005/07

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimentional seismic isolation technologies, as a part of the supporting R&D activities for the feasibility studeies on commercialized fast breeder reactor cycle systems. A reserch project by JAPC under the auspices of the Ministry of Economy,Trade, and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the reserch on the structural design technology. The reserch is reported in the following orderes, (1) Development till fiscal 2004, (2) Study on the 3-dimentional base isolation system (fiscal 2005), (3) Study on the guideline of 3-dimentional base isolation system, (4) Study on the vertical isolation system for main equiptment (fiscal 2005), (5) Study on the guideline of the vertical isolation system for main equipment.

JAEA Reports

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki; Kitamura, Seiji; Takahashi, Kenji; Inoue, Kazuhiko; Kida, Masanori; Moro, Satoshi*; Kato, Asao*; Fushimi, Minoru*

JNC TY9400 2004-028, 921 Pages, 2004/11

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies, as part of the supporting R&D activities for the feasibility studies on commercialized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy, Trade, and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the research on the structural design technology. The research scope was identified as (1) Study on Developing Program, (2) Study on 3-dimentional Entire Building Base Isolation System, and (3) Study on Vertical Isolation System for Main Equipment, and the results of this year's studies are summarized as follows. (1) Study on Developing Program -Performance Requirements for 3-dimensional Isolation Devices "The behavior of a three-dimensional isolated reactor building" and "amenity under the strong wind load" were studied in order to set up performance requirements for the three-dimensional isolation system. Consequently, it was proved for the former subject that the structure of horizontal base-dimensional isolated building was applicable to 3-D isolated building and for the latter that amenity of the operator in the 3-D isolated reactor building is not affected under the strong wind. -Development Targets and Schedules for Three-dimensional Isolation Deviece In order to select the development candidate of the three dimensional isolation devices, "evaluation items and criteria" and "technical guideline on seismic three-dimensional isolation system" were studied. For the former subject, detailed requirements to the component in the reactor building were studied based on the 2002 fiscal year result and embodied.(2) Study on 3-dimentional Entire Building Base Isolation System -The 3 system concepts nominated on 2001, "Hydraulic system", "Fiber reinforced air sp

Journal Articles

High speed lithium flow experiments for IFMIF target

Kondo, Hiroo*; Fujisato, Atsushi*; Yamaoka, Nobuo*; Inoue, Shoji*; Miyamoto, Seiji*; Sato, Fuminobu*; Iida, Toshiyuki*; Horiike, Hiroshi*; Matsushita, Izuru*; Ida, Mizuho*; et al.

Journal of Nuclear Materials, 329-333(Part1), p.208 - 212, 2004/08

 Times Cited Count:13 Percentile:65.61(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki; Kitamura, Seiji; Inoue, Kazuhiko; Kida, Masanori; Moro, Satoshi; Kato, Asao; Fushimi, Minoru*

JNC TY9400 2003-009, 682 Pages, 2003/05

JNC-TY9400-2003-009.pdf:35.1MB

Japan Nuclear Cycle Development Institute(JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies,as part of the supporting R&D activities for the feasibility studies on commercialized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy,Trade,and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the research on the structural design technology. The research scope was identified as (1) Study on Developing Program,(2) Study on 3-dimentional Entire Building Base Isolation System,and (3) Study on Vertical Isolation System for Main Equipment, and the results of this year's studies are summarized as follows.

Journal Articles

Water jet flow simulation and lithium free surface flow experiments for the IFMIF target

Ida, Mizuho*; Horiike, Hiroshi*; Akiba, Masato; Ezato, Koichiro; Iida, Toshiyuki*; Inoue, Shoji*; Miyamoto, Seiji*; Muroga, Takeo*; Nakamura, Hideo; Nakamura, Hiroshi*; et al.

Journal of Nuclear Materials, 307-311(Part2), p.1686 - 1690, 2002/12

 Times Cited Count:5 Percentile:35.53(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Analysis of misoriented crystal structure by ion channeling observed using ion-induced secondary electrons

Kudo, Hiroshi*; Sakamoto, Akihiko*; Yamamoto, Shunya; Aoki, Yasushi; Naramoto, Hiroshi; Inoue, Tomoyasu*; Sato, Msataka*; Yamamoto, Yasuhiro*; Umezawa, Kenji*; Seki, Seiji*

Japanese Journal of Applied Physics, Part 2, 35(11B), p.L1538 - L1541, 1996/11

no abstracts in English

Journal Articles

Electrical insulation and conduction coating for fusion experimental devices

Onozuka, Masanori*; Tsujimura, Seiji*; Toyoda, Masahiko*; Inoue, Masahiko*; Abe, Tetsuya; Murakami, Yoshio

Fusion Technology, 29(1), p.73 - 82, 1996/01

 Times Cited Count:9 Percentile:63.09(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of elevated temperature structural design standard and three-dimensional seismic isolation technology for advanced nuclear power plant

Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Takahashi, Kenji*; Ikutama, Shinya*; Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Kitamura, Seiji

no journal, , 

no abstracts in English

Oral presentation

Uncertainty analysis for initial defect scenario in geological disposal of high level waste

Inoue, Yoshihisa; Takeda, Seiji; Kimura, Hideo

no journal, , 

no abstracts in English

Oral presentation

The Precipitation behavior of $$gamma$$ double-prime (Ni$$_{3}$$Nb) in the high Ni steel

Sano, Keisuke*; Ono, Naoko*; Ukai, Shigeharu*; Hayashi, Shigenari*; Miura, Seiji*; Yamashita, Shinichiro; Inoue, Toshihiko

no journal, , 

no abstracts in English

Oral presentation

The Precipitation behavior of $$gamma$$ double-prime (Ni$$_{3}$$Nb) in the high Ni steel

Sano, Keisuke*; Ono, Naoko*; Ukai, Shigeharu*; Hayashi, Shigenari*; Miura, Seiji*; Yamashita, Shinichiro; Inoue, Toshihiko

no journal, , 

JAEA is study in the high Ni-alloy behavior as ODS substitute materials for the use in fast reactor. The precipitation behavior of $$gamma$$ double-prime (Ni$$_{3}$$Nb) in the high Ni steel was tested in prescription examinations. The results was the $$gamma$$ double-prime (Ni$$_{3}$$Nb) became a fault size and the hardness was decreased in the high prescription temperature and the long prescription time.

Oral presentation

Fabrication of insert coil with ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

no journal, , 

no abstracts in English

21 (Records 1-20 displayed on this page)