Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 100

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Upgrade of DC power supply system in ITER CS Model Coil Test Facility

Shimono, Mitsugu; Uno, Yasuhiro; Yamazaki, Keita; Kawano, Katsumi; Isono, Takaaki

JAEA-Testing 2014-004, 62 Pages, 2015/03

JAEA-Testing-2014-004.pdf:16.03MB

The ITER CS Model Coil Test Facility is composed of a helium refrigerator / liquefier system, a DC power supply system, a vacuum system and a data acquisition system. The DC power supply system supplies currents to two superconducting coils, the CS Model Coil and an insert coil. A 50-kA DC power supply is installed for the CS Model Coil and two 30 kA DC power supplies are installed for an insert coil. In order to evaluate superconducting performance of a conductor used for ITER Toroidal Field (TF) coils whose operating current is 68 kA, the line for an insert coil is upgraded. A 10-kA DC power supply was added, DC circuit breakers were upgraded, bus bars and current measuring instrument were replaced. In accordance to the upgrade, operation manual was revised.

JAEA Reports

Maintenance of helium refrigerator/liquefier system in ITER CS Model Coil Test Facility

Ebisawa, Noboru; Kiuchi, Shigeki*; Kikuchi, Katsumi*; Kawano, Katsumi; Isono, Takaaki

JAEA-Testing 2014-003, 37 Pages, 2015/03

JAEA-Testing-2014-003.pdf:11.7MB

Objective of the ITER CS Model Coil Test Facility is to evaluate a large scale superconducting conductor for fusion using the Central Solenoid (CS) Model Coil, which can generate a 13-T magnetic field in the inner bore with a 1.5m diameter. The facility is composed of a helium refrigerator / liquefier system, a DC power supply system, a vacuum system and a data acquisition system. This report describes that maintenance of the helium refrigerator / liquefier system since the Great East Japan Earthquake in March 2011 until the first operation after the earthquake in December 2012.

JAEA Reports

Development of module for TRU high temperature chemistry (Joint research)

Minato, Kazuo; Akabori, Mitsuo; Tsuboi, Takashi; Kurobane, Shiro; Hayashi, Hirokazu; Takano, Masahide; Otobe, Haruyoshi; Misumi, Masahiro*; Sakamoto, Takuya*; Kato, Isao*; et al.

JAERI-Tech 2005-059, 61 Pages, 2005/09

JAERI-Tech-2005-059.pdf:20.67MB

An experimental facility called the Module for TRU High Temperature Chemistry (TRU-HITEC) was installed in the Back-end Cycle Key Elements Research Facility (BECKY) of the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) for the basic studies of the behavior of the transuranium elements (TRU) in pyrochemical reprocessing and oxide fuels. TRU-HITEC consists of three alpha/gamma cells shielded by steel and polyethylene and a glove box shielded by leaded acrylic resin, where experimental apparatuses have been equipped and a high purity argon gas atmosphere is maintained. In the facility 10 g of $$^{241}$$Am as well as the other TRU of Np, Pu and Cm can be handled. This report summarizes the outline, structure, performance and interior apparatuses of the facility, and is the result of the joint research between the Japan Atomic Energy Research Institute and three electric power companies of Tokyo Electric Power Co., Tohoku Electric Power Co. and the Japan Atomic Power Co.

JAEA Reports

Cause investigation and repair of breakage of catalyst dust filter on mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system (Contract research)

Morisaki, Norihiro; Hayashi, Koji; Inagaki, Yoshiyuki; Kato, Michio; Fujisaki, Katsuo*; Maeda, Yukimasa; Mizuno, Sadao*

JAERI-Tech 2005-009, 37 Pages, 2005/03

JAERI-Tech-2005-009.pdf:14.33MB

The breakage of the catalyst dust filter was found at the nozzle flange, which was welded onto the end plate of the filter, by the bubbling test using nitrogen gas of the mock-up model test facility. We investigated the cause of breakage and devised a repairing method. The cause of the breakage was the stress corrosion cracking (SCC) generated from the inside of the filter. The filter was repaired based on the following countermeasures such as reduction of condensed water in the filter, tensile stress and sensitization at welding joints. Furthermore, the inspection was carried out to investigate the structural integrity of the welding joints in the test facility of which structure, material and operating condition were similar to the filter. As the results, it was confirmed that the structural integrity was maintained.

Journal Articles

Exhaust gas monitoring device of nuclear fusion experimental device

Kaminaga, Atsushi; Nakamura, Hirofumi; Isobe, Kanetsugu; Arai, Takashi

Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03

no abstracts in English

JAEA Reports

Annual report on operation, utilization and technical development of Hot Laboratories; April 1, 2001 to March 31, 2002

Department of Hot Laboratories

JAERI-Review 2002-039, 106 Pages, 2003/01

JAERI-Review-2002-039.pdf:9.46MB

no abstracts in English

Journal Articles

Stabilization control of flywheel generator systems having multiple synchronous machines

Inoue, Katsuhiko*; Ogasawara, Satoshi*; Matsukawa, Makoto

Denki Gakkai Kenkyukai Shiryo, Handotai Denryoku Henkan, Sangyo Denryoku Denki Oyo Godo Kenkyukai, p.45 - 50, 2002/11

no abstracts in English

JAEA Reports

Development of the flow-through diffusion system and improvements of the experimental methods

; Sato, Haruo

JNC-TN8410 2001-028, 36 Pages, 2002/03

JNC-TN8410-2001-028.pdf:1.81MB

For a safety assessment of the high-level radioactive waste disposal, effective diffusion coefficients (D$$_{e}$$) of radionuclides in bentonite have been accumulated by the through-diffusion method. It has been found recently that experimental results on D$$_{e}$$s for several cations (cesium and strontium) by the fairly standard experimental method in JNC differ from those previously reported in several papers. Discrepancy can be considered to be due to different design of diffusion cell and system. In order to confirm influences of the experimental design on cation diffusivities in bentonite, a flow-through diffusion system was developed and several diffusion experiments were conducted.As a result, magnitude of D$$_{e}$$ and its salinity dependence were relatively different between the standard and flow-through diffusion system. Since the latter system can control boundary conditions of the experiment more strictly than the standard method, we can conclude that the flow-through diffusion system provide correct results. In addition, we apply this flow-through diffusion system to a modification of controlling boundary condition during the experiment and to the diffusion experiment under controlled temperature.

JAEA Reports

Simulation tests for thermal characteristics of JCO precipitation vessel using a mock-up device

Watanabe, Shoichi; Miyoshi, Yoshinori; Yamane, Yuichi

JAERI-Tech 2002-043, 93 Pages, 2002/03

JAERI-Tech-2002-043.pdf:6.74MB

no abstracts in English

JAEA Reports

The data analysis of the single well injection-withdraw tracer experiment using the MACRO II

*; *;

JNC-TN8400 2001-012, 69 Pages, 2001/04

JNC-TN8400-2001-012.pdf:8.43MB

On understanding the radionuclide transport in natural barrier in radioactive waste isolation research, the macroscopic dispersion in heterogeneous permeability field in the underground rock is regarded as an important process. Therefore, we have conducted lots of tracer experiments by the MACRO II facility with an artificially constructed heterogeneous permeability field. In order to study the scale dependence of dispersion coefficients in case of laboratory experiments, we placed the flow cell horizontally, and conducted injection-withdraw tracer experiment with a single well. We have conducted I5 cases experiments. These cases were prepared by changing a position of single well and the injection-withdraw time. At each position we have conducted 9 cases and 6 cases experiments. In this report, we evaluated the macroscopic dispersion coefficients by the fitting of analytical solution to breakthrough curve measured by the 15 cases pumping tracer experiment. Consequently, we could evaluate the dispersion coefficients for 12 cases of 15 cases. Then, we discussed the relation between a injection-withdraw flow rate and a property of heterogeneous media and dispersion coefficient. The conclusions obtained from the results of the evaluation are summarized as follows, (1)It was found that the macroscopic dispersion coefficients tend to be increased with increase of the average radius of tracer front spread around a single well. (2)We have conducted any experiments with s single well settled at two positions. In case of that there is low permeability around a single well, we found dispersion coefficients are large. In case of that there is high permeability around a single well, we found dispersion coefficients are small. (3)In three cases that we could not evaluate because of incorrect accuracy of fitting, we have found it possible that there is some points that dispersion coefficients were strikingly small in tracer front.

JAEA Reports

Bending fatigue and its evaluation of ropes used in equipment for recovery of rare metals from seawater

Tamada, Masao; Kasai, Noboru; Seko, Noriaki; Hasegawa, Shin; Takeda, Hayato*; Katakai, Akio; Sugo, Takanobu

JAERI-Tech 2000-072, 40 Pages, 2000/12

JAERI-Tech-2000-072.pdf:10.9MB

no abstracts in English

Journal Articles

Numerical study on pressure rise characteristics in simulated ITER structural components during ingress-of-coolant events

Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime

Fusion Engineering and Design, 51-52, p.623 - 630, 2000/11

 Times Cited Count:1 Percentile:87.33(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Present state and future view of significant metals-recovery from seawater

Tamada, Masao; Seko, Noriaki

Isotope News, p.2 - 6, 2000/04

no abstracts in English

JAEA Reports

Design and manufacture of a testing device for the evaluation of optical elements

Shimizu, Yuichi; Yoda, Osamu; Sasuga, Tsuneo*; Teraoka, Yuden; Yokoya, Akinari; Yanagihara, Mihiro*

JAERI-Tech 2000-021, p.45 - 0, 2000/03

JAERI-Tech-2000-021.pdf:3.01MB

no abstracts in English

Journal Articles

Tritium confinement and detritiation demonstration program for fusion reactor rooms using caisson assembly for tritium safety study (CATS) at TPL/JAERI

Hayashi, Takumi; Kobayashi, Kazuhiro; Nishi, Masataka

Hoken Butsuri, 35(1), p.112 - 115, 2000/03

no abstracts in English

JAEA Reports

None

; *; ; *

JNC-TY6400 2000-013, 102 Pages, 2000/02

JNC-TY6400-2000-013.pdf:2.45MB

None

JAEA Reports

Numerical analysis on ingress-of-coolant events in fusion reactors with TRAC-PF1 code

Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

JAERI-Research 99-075, p.95 - 0, 2000/01

JAERI-Research-99-075.pdf:4.62MB

no abstracts in English

Journal Articles

Numerical prediction of two-phase flow behavior in a fusion reactor at an ingress-of-coolant event

Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

Nippon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, 1, p.609 - 610, 2000/00

no abstracts in English

Journal Articles

Numerical analysis on liquid-gas two-phase flow behavior in fusion reactors

Takase, Kazuyuki; Ose, Yasuo*; Suzuki, Takayuki*; Akimoto, Hajime

Nippon Kikai Gakkai Yamanashi Koenkai Koen Rombunshu (000-4), p.173 - 174, 2000/00

no abstracts in English

JAEA Reports

Extrusion analysis of buffer using diffusion model

; *

JNC-TN8400 99-040, 75 Pages, 1999/11

JNC-TN8400-99-040.pdf:9.08MB

The buffer material that will be buried as a component of the engineered barriers system swells when saturation by groundwater. As a result of this swelling, buffer material may penetrate into the peripheral rock zone surrounding the buffer through open fractures. If sustained for extremely in long-period of time, The buffer material extrusion could lead to reduction of buffer density, which may in turn degrade the assumed performance assessment properties (e.g., permeability, diffusion coefficient) JNC has been conducted the study of bentonite extrusion into fractures of rock mass as a part of high level waste research. In 1997, JNC has reported the test results concerning buffer material extrusion and buffer material erosion. These tests have been done using test facilities in Geological Isolation Basic Research Facility. After 1997, JNC also conducted analytical study of buffer material extrusion. This report describes the analysis results of this study which are reflected to the H12 report. In this analysis, The diffusion coefficient was derived as a function of the swelling pressure and the viscosity resistance of the buffer materials. Thus, the reduction in density of buffer materials after emplacement in saturated rock was assessed. The assessment was made assuming parallel-plate radial fractures initially filled by water only. Because fractures in natural rock masses inevitably have mineral inclusions inside of them and fractures orientation leads to fractures intersecting other fractures, this analysis gives significantly conservative conditions with respect to long-term extrusion of buffer and possible decrease in buffer density.

100 (Records 1-20 displayed on this page)