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.

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 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.

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

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

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

Suzuki, Satoru; 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) of radionuclides in bentonite have been accumulated by the through-diffusion method. It has been found recently that experimental results on Ds 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 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.

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

*; Kanazawa, Yasuo*;

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

JNC-TN8400-2001-012.pdf:6.87MB

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.

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

https://doi.org/10.1016/S0920-3796(00)00198-8

no abstracts in English

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

None

; *; Tokizawa, Takayuki; *

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

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

None

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

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

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

no abstracts in English