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Journal Articles

Development of remote pipe welding tool for divertor cassettes in JT-60SA

Hayashi, Takao; Sakurai, Shinji; Sakasai, Akira; Shibanuma, Kiyoshi; Kono, Wataru*; Onawa, Toshio*; Matsukage, Takeshi*

Fusion Engineering and Design, 101, p.180 - 185, 2015/12

 Times Cited Count:4 Percentile:33.51(Nuclear Science & Technology)

Remote pipe welding tool accessing from inside pipe has been newly developed for JT-60SA. Remote handling (RH) system is necessary for the maintenance and repair of in-vessel components such as lower divertor cassettes in JT-60SA. Cooling pipes, which connects between the divertor cassette and the vacuum vessel with bellows are required to be cut and welded in the vacuum vessel by RH system. The available space for RH system is very limited inside the vacuum vessel, especially around the divertor cassettes. Thus, the cooling pipes are required to be cut and weld from the inside in the vacuum vessel. The inner diameter, thickness and material of the cooling pipe are 54.2 mm, 2.8 mm and SUS316L, respectively. An upper pipe connected to the divertor cassette has a jut on the edge to fill the gap between pipes. Owing to the jut and two-times welding, the welding tool achieved the maximum allowable gap of 0.7 mm.

Journal Articles

A Sampling method of oriented small sample from fault cores for SEM observation

Shimada, Koji; Kametaka, Masao*; Nakayama, Kazuhiko; Seshimo, Kazuyoshi; Tanaka, Yoshihiro; Hayashi, Toshio*; Tanaka, Yukumo; Shimogama, Kota*; Okazaki, Kazuhiko*

Chishitsugaku Zasshi, 119(11), p.727 - 731, 2013/11

Staples for a stapler can be used as a frame of a small oriented sample taken from fragile and scarce fault gouge. The fault gouge was slotted for staples of an insert. Staples are a group of about ten or less ones holding right-angled three small surfaces. Pre-oriented staples set the slot would remove then presented for the SEM observation. Only a knife, some glues and simple equipment are needed for the method in the field or laboratories.

Journal Articles

Research and development of radiation measuring instruments for lake,pond and river sediments, 1

Yanagizawa, Koichi; Hayashi, Toshio*; Oinuma, Masaru*; Takemori, Makoto*; Ishikawa, Takanori*; Okaya, Tomoichi*; Nishigaki, Makoto*

Shadan Hojin Butsuri Tansa Gakkai Dai-129-Kai (Heisei-25-Nendo Shuki) Gakujutsu Koenkai Koen Rombunshu, p.287 - 288, 2013/10

The development of instrument aimed at the measurement of radiation dose in the sediment of lakes, rivers and sea bed been carried out. The radiation level contained in the sediment at the bottom of lake and so on is anticipated to indicate the existence of locally high radiation spots where the diffused radioactive substance is accumulated in ponds, rivers and lakes by rainwater. The radiation dose measurement system this time is to measure $$gamma$$-ray by dragging the detector, which is called probe, at the bottom of lakes to understand the radiation dose over wide areas. Furthermore, the measurement of resistivity value at the bottom of lakes is simultaneously dose to presume the condition of sediment.

JAEA Reports

Detaching test on an irradiated mock-up contaminated with tritium from the core of JMTR

Tomita, Kenji; Tsuchiya, Kunihiko; Onuma, Yuichi; Inoue, Shuichi; Watanabe, Hiroyuki; Saito, Takashi; Kikuchi, Taiji; Hayashi, Kimio; Kitajima, Toshio

JAEA-Technology 2008-036, 61 Pages, 2008/06

JAEA-Technology-2008-036.pdf:7.47MB

The second in-situ irradiation experiment using a mock-up (ORIENT-II, JMTR capsule Number: 99M-54J) with a tritium breeder (Li$$_{2}$$TiO$$_{3}$$) pebble bed in the Japan Materials Testing Reactor (JMTR) was finished on Aug. 1, 2006. Consideration on the detaching procedure of the irradiated mock-up contaminated with tritium with pebble bed and a detaching test of this mock-up was carried out. The tritium removal properties were examined in the irradiated mock-up, the sweep gas tube, the protective tube and the junction box, for the decreasing of the tritium release to the area of detaching test. Melting/enclosed tests of sealing plug were also carried out for the prevention of tritium leakage from sweep gas lines of pebble bed. Then, the detaching test of the pebble bed was carried out. This report describes the results of tritium removal tests, examination of the detaching procedure, and the detaching test, as well as knowledge obtained from these tests and works.

JAEA Reports

Investigation and design of the dismantling process of irradiation capsules containing tritium, 1; Conceptual investigation and basic design

Hayashi, Kimio; Nakagawa, Tetsuya; Onose, Shoji; Ishida, Takuya; Kodaka, Hideo; Katsuyama, Kozo; Kitajima, Toshio; Takahashi, Kozo; Tsuchiya, Kunihiko; Nakamichi, Masaru; et al.

JAEA-Technology 2008-010, 68 Pages, 2008/03

JAEA-Technology-2008-010.pdf:11.31MB

In-pile functional tests of breeding blankets for fusion reactors have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in ITER. The present report describes a conceptual investigation and a basic design of the dismantling process for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA. In the present design, the irradiation capsule is cut by a band saw; the released tritium is recovered safely by a purge-gas system, and is consolidated into a radioactive waste form. Furthermore, adoption of the inner-box enclosing the dismantling apparatus has brought a prospect to be able to utilize an existing hot cell (beta-$$gamma$$ cell) equipped with usual wall material permeable to tritium, without extensive refurbishing of the cell. Thus, the present study has indicated the feasibility of the present dismantling process for the irradiated JMTR capsules containing tritium.

Journal Articles

Fast collimated neutron flux measurement using stilbene scintillator and flashy analog-to-digital converter in JT-60U

Ishikawa, Masao*; Itoga, Toshio*; Okuji, Toshio*; Nakhostin, M.*; Shinohara, Koji; Hayashi, Takao; Sukegawa, Atsuhiko; Baba, Mamoru*; Nishitani, Takeo

Review of Scientific Instruments, 77(10), p.10E706_1 - 10E706_3, 2006/10

 Times Cited Count:21 Percentile:69.54(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Review of JAERI activities on the IFMIF liquid lithium target in FY2004

Nakamura, Hiroo; Ida, Mizuho*; Matsuhiro, Kenjiro; Fischer, U.*; Hayashi, Takumi; Mori, Seiji*; Nakamura, Hirofumi; Nishitani, Takeo; Shimizu, Katsusuke*; Simakov, S.*; et al.

JAERI-Review 2005-005, 40 Pages, 2005/03

JAERI-Review-2005-005.pdf:3.52MB

The International Fusion Materials Irradiation Facility (IFMIF) is being jointly planned to provide an accelerator-based Deuterium-Lithium (Li) neutron source to produce intense high energy neutrons (2 MW/m$$^{2}$$) up to 200 dpa and a sufficient irradiation volume (500 cm$$^{3}$$) for testing the candidate materials and components up to about a full lifetime of their anticipated use in ITER and DEMO. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid Li flow with a speed of 20 m/s. In target system, radioactive species such as 7Be, tritium and activated corrosion products are generated. In addition, back wall operates under severe conditions of neutron irradiation damage (about 50 dpa/y). In this paper, the thermal and thermal stress analyses, the accessibility evaluation of the IFMIF Li loop, and the tritium inventory and permeation of the IFMIF Li loop are summarized as JAERI activities on the IFMIF target system performed in FY2004.

Journal Articles

Achievement of reactor-outlet coolant temperature of 950$$^{circ}$$C in HTTR

Fujikawa, Seigo; Hayashi, Hideyuki; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo; Nakagawa, Shigeaki; Sakaba, Nariaki

Journal of Nuclear Science and Technology, 41(12), p.1245 - 1254, 2004/12

 Times Cited Count:87 Percentile:97.76(Nuclear Science & Technology)

A High Temperature Gas-cooled Reactor (HTGR) is particularly attractive due to its capability of producing high-temperature helium gas and to its inherent safety characteristics. The High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan, achieved its rated thermal power of 30MW and reactor-outlet coolant temperature of 950$$^{circ}$$C on 19 April 2004. During the high-temperature test operation which is the final phase of the rise-to-power tests, reactor characteristics and reactor performance were confirmed, and reactor operations were monitored to demonstrate the safety and stability of operation. The reactor-outlet coolant temperature of 950$$^{circ}$$C makes it possible to extend high-temperature gas-cooled reactor use beyond the field of electric power. Also, highly effective power generation with a high-temperature gas turbine becomes possible, as does hydrogen production from water. The achievement of 950$$^{circ}$$C will be a major contribution to the actualization of producing hydrogen from water using the high-temperature gas-cooled reactors. This report describes the results of the high-temperature test operation of the HTTR.

Journal Articles

JAERI completed performance tests of the High Temperature Engineering Test Reactor (HTTR) at 950$$^{circ}$$C

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo

Nihon Genshiryoku Gakkai-Shi, 46(8), P. 510, 2004/08

no abstracts in English

Journal Articles

High Temperature Engineering Test Reactor (HTTR) of JAERI achieved the reactor outlet helium gas temperature of 950$$^{circ}$$C for the first time in the world

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo

Nihon Genshiryoku Gakkai-Shi, 46(5), P. 301, 2004/05

no abstracts in English

JAEA Reports

Irradiation experiments of the 13th-15th OGL-1 fuel assemblies

Hayashi, Kimio; Sawa, Kazuhiro; Shiratori, Tetsuo; Kikuchi, Hironobu; Fukuda, Kosaku; Kitajima, Toshio; Ito, Tadaharu; Waragai, Hyota

JAERI-Research 2000-001, p.116 - 0, 2000/01

JAERI-Research-2000-001.pdf:21.78MB

no abstracts in English

Journal Articles

Meta-scheduling for a cluster of supercomputers

; Hirayama, Toshio; *; Hayashi, Takuya*; Kasahara, Hironori*

Int. Conf. on Supercomputing,Workshop 1;Scheduling Algorithms for Parallel-Distributed Computing, p.63 - 69, 1999/00

no abstracts in English

JAEA Reports

Study on TRU transmutation by LMFBRs,1; Study on FBR core concepts for TRU transmution

Yamaoka, Mitsuaki; Ishikawa, Makoto; Hayashi, Hideyuki; Wakabayashi, Toshio

PNC TN9410 91-365, 368 Pages, 1991/11

PNC-TN9410-91-365.pdf:8.03MB

A study was performed on TRU transmutation by LMFBRs. This report describes the results of the items shown below. (1) Study on a super long life core loaded with TRU. A feasibility study was performed on a super long life core loaded with TRU fuel which operates without fuel exchange during 30 years. Its advantage is that it can transmute TRU with storing it in the core during plant life time. I It was found that reactivity change and power variation due to burnup can be reduced remarkably by optimizing TRU loading amount and region. Also, it was found that a 1000 MWe core can transmute TRU of 10 ton which comes from 13 LWRs. (2) Study on a heterogeneous core loaded with TRU. The radial hderogeneous core is one of the candidate concepts for TRU transmutation because the internal blanket may be loaded with larger amount of TRU than the core fuel. It was found that the core loaded with large amount of TRU in the internal blanket can transmute TRU several times more than the homogeneous core with no significant in fluence on core characteristics. (3) Study on a method for TRU loading in a subassembly. A TRU loading method was studied where both TRU loaded fuel pins and the MOX fuel pins are arranged in a subassembly aiming at reducing the number of TRU loaded fuel pins. Results are shown with a focus on power distribution in a subassembly.

Journal Articles

None

Ishikawa, Makoto; Hayashi, Hideyuki*; Kamei, Takanobu*; Sanda, Toshio*; Kawakita, Takashi*

Donen Giho, (77), p.92 - 96, 1991/03

None

Oral presentation

Development of the electrolytic and thermochemical hybrid hydrogen production process for FBR

Hayashi, Hideyuki; Nakagiri, Toshio; Yamaki, Tetsuya; Asano, Masaharu

no journal, , 

no abstracts in English

Oral presentation

Neutron emission profile measurements with fast digital signal processor in JT-60U

Ishikawa, Masao*; Itoga, Toshio*; Okuji, Toshio*; Nakhostin, M.*; Shinohara, Koji; Hayashi, Takao; Morioka, Atsuhiko; Baba, Mamoru*; Nishitani, Takeo

no journal, , 

no abstracts in English

Oral presentation

Fast neutron emission profile measurements using a digital signal processing technique in JT-60U

Ishikawa, Masao; Itoga, Toshio*; Okuji, Toshio*; Baba, Mamoru*; Shinohara, Koji; Hayashi, Takao; Sukegawa, Atsuhiko

no journal, , 

no abstracts in English

Oral presentation

Development of fast measurement system of neutron emission profiles using digital signal processing technique

Ishikawa, Masao; Itoga, Toshio*; Okuji, Toshio*; Nakhostin, M.*; Baba, Mamoru*; Shinohara, Koji; Hayashi, Takao; Sukegawa, Atsuhiko; Nishitani, Takeo

no journal, , 

Line-integrated neutron emission profiles are routinely measured using Stilbene neuron detectors (SNDs) in JT-60U tokamak. Although the SND has excellent pulse shape discrimination (PSD) property between neutrons and $$gamma$$ rays, the maximum count rate is limited up to $$sim$$ 10$$^{5}$$ cps due to its analog circuit. To overcome this issue, a digital signal processing (DSP) system using a flash ADC has been developed. In this system, anode signals from the photomultiplier of the SND are directory stored and digitized in the Flash ADC. Then, the PSD is performed using software. The DSP system has been installed in JT-60U and started to measure neutrons in deuterium experiments. As a result, it is confirmed that the DSP system is successfully measured neutron fluxes with count rate up to 10$$^{6}$$ cps.

Oral presentation

Cerebral methodology based computing for estimating validity of simulation results

Suzuki, Yoshio; Nishida, Akemi; Yamada, Tomonori; Araya, Fumimasa; Hayashi, Sachiko; Nakajima, Norihiro; Hirayama, Toshio

no journal, , 

Our challenge is to estimate the validity of simulation results by establishing "Cerebral Methodology Based Computing (CMC)". The estimation of the validity is indispensable to accurately predict phenomena by using simulation. It is difficult to estimate the validity from a single simulation because the simulation contains uncertainties and ambiguities. We have proposed CMC as the computing methodology which enables us to estimate the validity of results with both deductive and inductive approaches, similar to the human thinking process. To realize CMC, we have constructed the system which enables us to execute both deductive simulations and inductive simulations, and then combine results of those simulations in an integration process. We have applied the system to a thermal displacement analysis of a nuclear power plant and confirmed the usefulness of the system.

Oral presentation

Microstructure observation of oriented samples from fault zone using scanning electron microscope

Nakayama, Kazuhiko; Shimada, Koji; Seshimo, Kazuyoshi; Tanaka, Yoshihiro; Kametaka, Masao*; Okazaki, Kazuhiko*; Shimogama, Kota*; Hayashi, Toshio*

no journal, , 

no abstracts in English

24 (Records 1-20 displayed on this page)