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Journal Articles

Evaluation of Tsunami debris impact on Tokai Reprocessing Plant

Nishino, Saki; Tsuboi, Masatoshi; Okada, Jumpei; Saegusa, Yu; Omori, Kazuki; Yasuo, Kiyoshi; Seshimo, Kazuyoshi; Domura, Kazuyuki; Yamamoto, Masahiko

Nihon Hozen Gakkai Dai-17-Kai Gakujutsu Koenkai Yoshishu, p.541 - 548, 2021/07

no abstracts in English

Journal Articles

Analysis of residual stress in steel bar processed by cold drawing and straightening

Nishida, Satoru*; Nishino, Soichiro*; Sekine, Masahiko*; Oka, Yuki*; Harjo, S.; Kawasaki, Takuro; Suzuki, Hiroshi; Morii, Yukio*; Ishii, Yoshinobu*

Materials Transactions, 62(5), p.667 - 674, 2021/05

 Times Cited Count:1 Percentile:0(Materials Science, Multidisciplinary)

JAEA Reports

Case studies of radiation dose assessment in emergency situation of nuclear facilities

Kawasaki, Masatsugu; Nakajima, Junya; Yoshida, Keisuke; Kato, Saori; Nishino, Sho; Nozaki, Teo; Nakagawa, Masahiro; Tsunoda, Junichi; Sugaya, Yuki; Hasegawa, Rie; et al.

JAEA-Data/Code 2017-004, 57 Pages, 2017/03

JAEA-Data-Code-2017-004.pdf:2.34MB

In emergency situation of nuclear facilities, we need to estimate the radiation dose due to radiation and radioactivity to grasp the influence range of the accident in the early stage. Therefore, we prepare the case studies of dose assessment for public exposure dose and personal exposure dose and contribute them to emergency procedures. This document covers about accidents of nuclear facilities in Nuclear Science Research Institute and past accident of nuclear power plant, and it can be used for inheritance of techniques of emergency dose assessment.

Journal Articles

Development of methods for removing the deposit in the combustion chamber of the water tube boiler

Kawasaki, Ichio; Ishiyama, Toru; Nishino, Shohei; Aoki, Masaru*

Boira Kenkyu, (391), p.8 - 14, 2015/06

no abstracts in English

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)

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2013

Watanabe, Hitoshi; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Goto, Ichiro*; Kibe, Satoshi*; et al.

JAEA-Review 2014-040, 115 Pages, 2015/01

JAEA-Review-2014-040.pdf:4.26MB

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 bylaw 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 2013. 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.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2012

Sumiya, Shuichi; Watanabe, Hitoshi; Miyagawa, Naoto; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki; Otani, Kazunori*; Hiyama, Yoshinori*; et al.

JAEA-Review 2013-041, 115 Pages, 2014/01

JAEA-Review-2013-041.pdf:19.01MB

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, and the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), this report describes the effluent control results of liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2012, from 1st April 2012 to 31st March 2013. 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 facilities were much lower than the authorized limits of the above regulations.

Journal Articles

High-resolution photoemission study of the hybridization gap in the Kondo semiconductor CeRhAs

Shimada, Kenya*; Higashiguchi, Mitsuharu*; Arita, Masashi*; Namatame, Hirofumi*; Taniguchi, Masaki*; Fujimori, Shinichi; Saito, Yuji; Fujimori, Atsushi; Takata, Yasutaka*; Shin, S.*; et al.

Journal of Magnetism and Magnetic Materials, 310(2, Part1), p.e57 - e58, 2007/03

We have examined the electronic states of the Kondo semiconductor CeRhAs and the semimetal CeRhSb by means of high-resolution photoemission spectroscopy using tunable photon energies from 40 up to 5948 eV. On the basis of the photon-energy dependence ofthe photoionization cross-section, we have elucidated the p-d-f hybridized states in these compounds.

Journal Articles

Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

 Times Cited Count:2 Percentile:6.67(Physics, Fluids & Plasmas)

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-$$beta$$. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Chujo, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

no abstracts in English

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

 Times Cited Count:33 Percentile:70.69(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

None

Sekiguchi, Nobutada; Nishino, Osamu*; Wakayama, Naoaki*; Iwasaki, Toshio*; Araki, Hitoshi*; Miyazawa, Tatsuo*

Nihon Genshiryoku Gakkai-Shi, 22(9), p.604 - 615, 1980/00

Oral presentation

Development of removal method for the deposit in the boiler system

Nishino, Shohei; Ishiyama, Toru; Kawasaki, Ichio

no journal, , 

The purpose of this R&D is the development of removal method for the deposit and the countermeasure of corrosion by solute in the boiler system. In the boiler system, sulfur and iron oxide accumulated on the bottom and stiffened on there. Because the property of this deposit changed to strong acidity, then the generating tube was corroded by it. And the leakage, occurred at generating tube, was found at Dec. 2011. The property of deposit was too hard to remove by pressurized water, and width of each pipe was too narrow to remove by mechanical method, because there was several thousands of generating tube every 30 mm on the bottom. Therefore the effect of lab examination, corrosion test based on materials of the generated tube, was evaluated.

Oral presentation

Development of moderated neutron calibration field using RI sources in JAEA-FRS

Nishino, Sho; Tanimura, Yoshihiko; Ebata, Yoshiaki*; Yoshizawa, Michio; Yoshitomi, Hiroshi; Kawasaki, Katsuya

no journal, , 

no abstracts in English

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

Oral presentation

Characteristics of current sharing temperature of ITER CS insert conductor

Nabara, Yoshihiro; Suwa, Tomone; Ozeki, Hidemasa; Sakurai, Takeru; Kajitani, Hideki; Iguchi, Masahide; Hemmi, Tsutomu; Shimono, Mitsugu; Ebisawa, Noboru; Sato, Minoru; et al.

no journal, , 

no abstracts in English

Oral presentation

Test results of CS insert for ITER; Test method

Isono, Takaaki; Kawano, Katsumi; Ozeki, Hidemasa; Saito, Toru; Nabara, Yoshihiro; Suwa, Tomone; Shimono, Mitsugu; Ebisawa, Noboru; Sato, Minoru; Uno, Yasuhiro; et al.

no journal, , 

JAEA is procuring conductors for ITER Central Solenoid (CS) and has evaluated its superconducting performance using CS Model Coil Test facility. We measured Tcs values during cyclic charge of 16,000 cycles and warm-up and cool-down cycle of 3 times. And we measured effect of coil deformation by electro-magnetic force on Tcs values and performed quench test. In this presentation, test method will be reported.

Oral presentation

Development of powder recovery technology by laser and examination of applicability toward decommissioning of reprocess plant

Okada, Jumpei; Nishino, Saki; Terunuma, Ryuki; Takahashi, Naoki; Isomae, Hidemi

no journal, , 

no abstracts in English

Oral presentation

The Dose-reduction activity of the lens of the eye at Tokai Reprocessing Plant

Nishino, Saki; Nemoto, Ryo*; Hayashi, Hiroyuki*; Kobayashi, Daisuke; Isomae, Hidemi; Sakuma, Shuhei; Takimoto, Misaki; Okuyama, Shun; Unno, Motoyoshi; Kitao, Takahiko

no journal, , 

At the JAEA Tokai Reprocessing facility, especially workers engaged in Plutonium Conversion Development Facility (PCDF) are required strict radiation control due to working environment handling various nuclear material including plutonium (Pu) at short range. Because the equivalent dose limit of the lens of the eye stipulated by Japanese regulations has been revised downwards, we reassessed personal dose equivalent focusing on the lens of the worker's eye. The reassessment results indicate that wearing the appropriate radiation protection glasses is necessary for some workers who handle Pu including waste material in PCDF. Radiation management using protective glasses has started under revised radiation control plan.

Patent

水管ボイラ内の堆積物除去方法及び装置

川崎 一男; 石山 道; 西野 将平

田村 欣也*

JP, 2014-104370  Patent licensing information  Patent publication (In Japanese)

【課題】水管ボイラ内が複雑かつ狭隘であっても、安価で、かつ簡略な構造で、洗浄対象物である水管に付着した堆積物の剥離を効率よく実現できる水管ボイラ内の堆積物除去方法及び装置を提供する 【解決手段】水管ボイラ内に圧力を印加した洗浄体を噴射させ、水管部外表面を洗浄する水管ボイラ内の堆積物除去方法であって、ドライアイスと圧縮空気とを混合する洗浄機本体と、前記洗浄機本体で製造したドライアイスと圧縮空気との混合気体である洗浄体を延長管ならびに噴射ノズルによって水管部外表面に吹き付けるノズル部とで構成し、水管部外表面に付着した堆積物を剥離する。

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