Refine your search:     
Report No.
 - 
Search Results: Records 1-18 displayed on this page of 18
  • 1

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

Improvement in oil seal performance of Gas Compressor in HTTR

Oyama, Sunao*; Hamamoto, Shimpei; Kaneshiro, Noriyuki*; Nemoto, Takahiro; Sekita, Kenji; Isozaki, Minoru; Emori, Koichi; Ito, Yoshiteru*; Yamamoto, Hideo*; Ota, Yukimaru; et al.

JAEA-Technology 2007-047, 40 Pages, 2007/08

JAEA-Technology-2007-047.pdf:18.83MB

High-Temperature engineering Test Reactor (HTTR) built by Japan Atomic Energy Agency (JAEA) has commonly used reciprocating compressor to extract helium gas and discharge helium gas into primary/secondary coolant helium loop from helium purification system. Rod-seal structure of the compressor is complicated from a prevention coolant leak standpoint. Because of frequently leakage of seal oil in operation, Rod seal structure isn't as reliable as it should be sustainable in the stable condition during long term operation. As a result of investigations, leakage's root is found in that seal were used in a range beyond limit sliding properties of seal material. Therefore a lip of the seal was worn and transformed itself and was not able to sustain a seal function. Endurance test using materials testing facility and verification test using a actual equipment on candidate materials suggest that a seal of fluorine contained resin mixed graphite is potentially feasible material of seal.

JAEA Reports

Report of investigation on malfunction of reserved shutdown system in HTTR

Hamamoto, Shimpei; Iigaki, Kazuhiko; Shimizu, Atsushi; Sawahata, Hiroaki; Kondo, Makoto; Oyama, Sunao; Kawano, Shuichi; Kobayashi, Shoichi; Kawamoto, Taiki; Suzuki, Hisashi; et al.

JAEA-Technology 2006-030, 58 Pages, 2006/03

JAEA-Technology-2006-030.pdf:10.69MB

During normal operation of High Temperature engineering Test Reactor (HTTR) in Japan Atomic Energy Agency (JAEA), the reactivity is controlled by the Control Rods (CRs) system which consists of 32 CRs (16 pairs) and 16 Control Rod Drive Mechanisms (CRDMs). The CR system is located in stand-pipes accompanied by the Reserved Shutdown System (RSS). In the unlikely event that the CRs fail to be inserted, the RSS is provided to insert B$$_{4}$$C/C pellets into the core. The RSS shall be designed so that the reactor should be held subcriticality from any operation condition by dropping in the pellets. The RSS consists of B$$_{4}$$C/C pellets, hoppers which contain the pellets, electric plug, driving mechanisms, guide tubes and so on. In accidents when the CRs cannot be inserted, an electric plug is pulled out by a motor and the absorber pellets fall into the core by gravity. A trouble, malfunction of one RSS out of sixteen, occurred during a series of the pre-start up checks of HTTR on February 21, 2005. We investigated the cause of the RSS trouble and took countermeasures to prevent the issue. As the result of investigation, the cause of the trouble was attributed to the following reason: In the motor inside, The Oil of grease of the multiplying gear flowed down from a gap of the oil seal which has been deformed and was mixed with abrasion powder of brake disk. Therefore the adhesive mixture prevented a motor from rotating.

JAEA Reports

Evaluation of heat exchange performance for secondary pressurized water cooler in HTTR

Tochio, Daisuke; Watanabe, Shuji; Saikusa, Akio; Oyama, Sunao; Nemoto, Takahiro; Hamamoto, Shimpei; Shinohara, Masanori; Isozaki, Minoru; Nakagawa, Shigeaki

JAEA-Technology 2006-005, 83 Pages, 2006/02

JAEA-Technology-2006-005.pdf:6.09MB

In High Temperature Engineering Test Reactor (HTTR), the rated thermal power of 30MW, the generated heat at reactor core is finally dissipated at the air-cooler by way of the heat exchangers of the primary cooling system, such as the intermediate heat exchanger (IHX) and the secondary pressurized water cooler (SPWC). The heat exchangers in the main cooling system are required the heat exchange performance to remove the reactor-generated-heat of 30MW under the condition of reactor coolant outlet temperature of 850 $$^{circ}$$C/ 950 $$^{circ}$$C. Therefore, the heat exchanges are required to satisfy the design criteria of heat exchange performance. In this report, heat exchange performance of the SPWC in the main cooling system was evaluated with the rise-to-power-up test and the in-service operation data. Moreover, evaluated value is compared with designed one, it is confirmed that the SPWC has required heat exchange performance.

JAEA Reports

Change in heat exchange performance of VCS cooler and its recovery works

Hamamoto, Shimpei; Watanabe, Shuji; Oyama, Sunao*; Ota, Yukimaru; Tochio, Daisuke; Fujimoto, Nozomu

JAERI-Tech 2005-035, 35 Pages, 2005/07

JAERI-Tech-2005-035.pdf:2.54MB

The Vessel Cooling System (VCS) is one of the safety engineered features of the HTTR. The VCS removes the decay heat of the reactor core when the forced circulation can not be maintained due to pipe rupture accidents, etc. VCS cools the core by water cooling panels surrounding the reactor pressure vessel. The VCS also keeps the temperature of the concrete of the primary shielding under the design limit during the operation. The temperature of cooling water of the VCS has recently tended to rise gradually, though the amount of heat removal of VCS has been constant. Accompanying with the increase of the cooling water temperature, the temperature of the shielding concrete is also possible to rise and exceed the limit. The heat exchange performance of the VCS cooler was evaluated and the deterioration of the cooler was verified. Therefore, the cleaning of heat transfer tubes was carried out to recover the heat exchange performance. The cleaning recovered the performance of the VCS cooler drastically and the cooling water temperature of the VCS could be reduced sufficiently.

JAEA Reports

Replacement of the filter for primary helium circulators of the HTTR

Furusawa, Takayuki; Sumita, Junya; Ueta, Shohei; Nemoto, Takahiro; Oyama, Sunao*; Kamata, Takashi

JAERI-Tech 2004-024, 46 Pages, 2004/03

JAERI-Tech-2004-024.pdf:6.75MB

Primary helium circulators of the HTTR are the important component as the helium gas which is reactor coolant, and three circulators for the primary pressurized water cooler and one for the intermediate heat exchanger are installed in primary cooling system. In the upstream of these circulators, the filter has been installed in order to suppress that it is entrapped in the bearing in which fine particles in helium gas, support main shaft of the helium circulator. The differential pressure of this filter rose gradually during rise-to-power test. The rise of the filter differential pressure of the helium circulator may cause the problem for reactor operation. Therefore, the filters were newly manufactured, and replacement of the filter was carried out. In replacement of the filter, appearance confirmation was carried out and deposit of the filter was analyzed. This paper described replacement of the filter and filter differential pressure rise investigation of the causes.

Journal Articles

Diagnostics system of JT-60U

Sugie, Tatsuo; Hatae, Takaki; Koide, Yoshihiko; Fujita, Takaaki; Kusama, Yoshinori; Nishitani, Takeo; Isayama, Akihiko; Sato, Masayasu; Shinohara, Koji; Asakura, Nobuyuki; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.482 - 511, 2002/09

 Times Cited Count:6 Percentile:3.03(Nuclear Science & Technology)

The diagnostic system of JT-60U (JT-60upgrade) is composed of about 50 individual diagnostic devices. Recently, the detailed radial profile measurements of plasma parameters have been improved, so that the internal structure of plasmas has been explored. The understanding of plasma confinement has been enhanced by density and temperature fluctuation measurements using a mm-wave reflectometer and electron cyclotron emission measurements respectively. In addition, the real-time control experiments of electron density, neutron yield, radiated power and electron temperature gradient have been carried out successfully by corresponding diagnostic devices. These measurements and the real time control contribute to improving plasma performance. Diagnostic devices for next generation fusion devices such as a CO2 laser interferometer/polarimeter and a CO2 laser collective Thomson scattering system have been developed.

Oral presentation

Helium chemistry in high-temperature gas-cooled reactors; Chemical impurity behaviour in the secondary Helium coolant of the HTTR

Hamamoto, Shimpei; Oyama, Sunao; Emori, Koichi; Umeda, Masayuki; Sakaba, Nariaki

no journal, , 

no abstracts in English

Oral presentation

Design study of small-sized high temperature gas-cooled reactor (MHR-50/100is), 4; Study for core physics and safety

Nakagawa, Shigeaki; Kunitomi, Kazuhiko; Tachibana, Yukio; Terada, Atsuhiko; Minatsuki, Isao*; Oyama, Sunao*; Tsukamoto, Hiroki*

no journal, , 

no abstracts in English

Oral presentation

Design study of small-sized high temperature gas-cooled reactor (MHR-50/100is), 1; Outline of development of small-sized high temperature gas-cooled reactor concept

Shimizu, Katsusuke*; Minatsuki, Isao*; Otani, Tomomi*; Mizokami, Yoritaka*; Oyama, Sunao*; Tsukamoto, Hiroki*; Kunitomi, Kazuhiko; Tachibana, Yukio; Terada, Atsuhiko

no journal, , 

no abstracts in English

Oral presentation

Solvent extraction of Mo and W for redox studies of Sg

Miyashita, Sunao; Toyoshima, Atsushi; Oe, Kazuhiro; Asai, Masato; Sato, Tetsuya; Kitatsuji, Yoshihiro; Tsukada, Kazuaki; Nagame, Yuichiro; Sch$"a$del, M.; Omtvedt, J. P.*; et al.

no journal, , 

For determination of the redox potentials of seaborgium (Sg), we plan to carry out rapid continuous experiments using a new system combined with a flow electrolytic column and the rapid liquid-liquid extraction apparatus SISAK. For the experiments of redox potentials of Sg, fast separation between different oxidation states of Sg is required. In this study, solvent extraction of W and Mo, as the lighter homologues of Sg, from 0.10 mol/L hydrochloric acid solution into di-(2-ethylhexyl)phosphoric acid (HDEHP), 1-phenyl-3-metyl-4-benzoyl-5-pyrazolone (PMBP) and 3-isopropyl-tropolone (HT) in toluene was investigated. A synergistic effect by tributylphosphate (TBP) was also examined.

Oral presentation

Electrolytic reduction of Mo and W as lighter homologues of seaborgium (Sg)

Toyoshima, Atsushi; Miyashita, Sunao; Oe, Kazuhiro; Asai, Masato; Sato, Tetsuya; Tsukada, Kazuaki; Kitatsuji, Yoshihiro; Nagame, Yuichiro; Sch$"a$del, M.; Omtvedt, J. P.*; et al.

no journal, , 

We plan to determine the redox potential of seaborgium (Sg) in continuous experiments with a flow electrolytic column and a continuous solvent extraction SISAK. In this study, reduction experiments of its lighter homologues, Mo and W, were performed using the flow electrolytic column apparatus. After 200 $$mu$$L of the $$^{181}$$W radiotracer in 0.1 M HCl was introduced into the apparatus, 1000 $$mu$$L of 0.1 M HCl was fed into the electrode on which an potential was applied between -0.8 and 0.6 V. 1000 $$mu$$L was taken from the effluent from the electrode and was then mixed with 10$$^{-4}$$ M hinokitiol in toluene with the same volume. After shaking for 1 min and then centrifuging for 30 s, 800 $$mu$$L was taken from each phase, which was then separately subjected to $$gamma$$-ray spectrometry. As a result, the extraction yield of $$^{181}$$W was constant against the variation of the applied potential. It seems that once reduced W was again oxidized to the +6 state in the extraction procedure.

Oral presentation

Improvement of rapid liquid-liquid extraction apparatus SISAK for redox studies of Sg

Oe, Kazuhiro; Tsukada, Kazuaki; Asai, Masato; Sato, Tetsuya; Toyoshima, Atsushi; Miyashita, Sunao; Nagame, Yuichiro; Sch$"a$del, M.; Kaneya, Yusuke*; Lerum, H. V.*; et al.

no journal, , 

We are planning to investigate the redox potentials of element 106, seaborgium, with a combination of the rapid liquid-liquid extraction apparatus SISAK and a flow electrolytic column. In order to combine these two apparatuses, we need to reduce the liquid flow-rate of the SISAK system. In this study, a new degasser, which works with a lower flow rate, was developed for SISAK. It separates the gas-liquid mixture using a hydrophobic Teflon membrane (only the gas can go through the membrane). Using this new degasser, dissolution efficiencies of gas-jet transported products were measured. At the typical flow rate for the SISAK system (0.4 mL/s), a dissolution efficiency of approximately 80% was obtained. A high yield of around 80% was also observed at a flow rate of 0.1 mL/s with a mixer for the gas-liquid mixing.

Oral presentation

Solvent extraction of hexavalent Mo and W using 4-isopropyltropolone (Hinokitiol) for seaborgium (Sg) reduction experiment

Miyashita, Sunao; Toyoshima, Atsushi; Oe, Kazuhiro*; Asai, Masato; Sato, Tetsuya; Tsukada, Kazuaki; Nagame, Yuichiro; Sch$"a$del, M.; Kaneya, Yusuke; Haba, Hiromitsu*; et al.

no journal, , 

Solvent extraction of $$^{93m}$$Mo and $$^{176}$$W using 4-isopropyltropolone (Hinokitiol, HT) was investigated. Extraction mechanism of Mo and W with HT was examined by slope analysis. The slopse of the distribution ratio of Mo and W vs. [HT] in logarithmic scale are 1.88 and 1.54, respectively.

Oral presentation

Extraction behavior of hexavalent and reduced Mo and W with 4-isopropyltropolone (Hinokitiol)

Miyashita, Sunao; Toyoshima, Atsushi; Oe, Kazuhiro*; Sato, Tetsuya; Asai, Masato; Tsukada, Kazuaki; Nagame, Yuichiro; Sch$"a$del, M.; Kaneya, Yusuke; Haba, Hiromitsu*; et al.

no journal, , 

The extraction behavior of hexavalent and reduced Mo and W were investigated when aqueous phase was 0.1 M HCl/0.9 M LiCl solution. The D value of Mo was changed from 10 to 1 when applied potential was near 0 to -0.2 V. On the other hand, the D value of W was not changed at all applied potentials in this experimental condition. Those results indicated that Mo was reduced by FEC, and the extraction behavior of reduced Mo was different from hexavalent Mo. In the case of W, W was not reduced or the D values of reduced W was same as hexavalent W.

Oral presentation

Chemical studies of Mo and W in preparation of a Seaborgium (Sg) reduction experiment using MDG, FEC, and SISAK

Toyoshima, Atsushi; Miyashita, Sunao*; Asai, Masato; Sato, Tetsuya; Kaneya, Yusuke; Tsukada, Kazuaki; Kitatsuji, Yoshihiro; Nagame, Yuichiro; Sch$"a$del, M.; Lerum, H. V.*; et al.

no journal, , 

To carry out a continuous reduction experiment of Sg with the low production rates and the short half-life, we are developing a new chemistry assembly consisting of a membrane degasser (MDG), a flow electrolytic column (FEC), the continuous liquid-liquid extraction apparatus, and the liquid scintillation counting system (SISAK). Recently, we have begun preparatory studies with Mo and W isotopes. Aqueous solution dissolving Mo and W was successfully separated from a carrier gas. Redox couples of Mo(VI)/Mo(V) and W(VI)/W(V) in HCl have been characterized for their macro amounts. Extraction behavior of Mo(VI) and W(VI) between toluene containing hinokitiol (HT) and HCl was successfully observed by a batch method. On-line extractions of short-lived Mo and W were also carried out using SISAK and MDG. In the symposium, our present status of the preparation with Mo and W will be presented.

Oral presentation

Electrolytic reduction studies of Mo and W towards the reduction of seaborgium

Toyoshima, Atsushi; Asai, Masato; Attallah, M. F.*; Goto, Naoya*; Gupta, N. S.*; Haba, Hiromitsu*; Huang, M.*; Kanaya, Jumpei*; Kaneya, Yusuke; Kasamatsu, Yoshitaka*; et al.

no journal, , 

Towards electrolytic reduction of Sg, batch-wise electrolytic reduction of carrier-free $$^{93m}$$Mo and $$^{176,181}$$W radiotracers was studied using a flow electrolytic column (FEC). The electrolyzed samples from a FEC were chemically analyzed by solvent extraction with TOA and HDEHP to separate and identify reduced species from the stable Mo(VI) and W(VI) ones based on their different extraction behavior. $$^{93m}$$Mo and $$^{176, 181}$$W were applied as radiotracers. We also performed cyclic voltammetry and UV/Vis absorption spectrometry of macro amounts of Mo and W in acidic solutions to obtain information on redox reactions of these elements under given conditions. In the conference, the present status of the preparatory reduction experiments with Mo and W will be presented.

Oral presentation

Electrolytic reduction of Mo and W as lighter homologues of seaborgium

Toyoshima, Atsushi; Miyashita, Sunao*; Oe, Kazuhiro*; Kitayama, Yuta*; Lerum, H. V.*; Goto, Naoya*; Kaneya, Yusuke; Komori, Yukiko*; Mitsukai, Akina*; Vascon, A.; et al.

no journal, , 

no abstracts in English

Oral presentation

Developments towards aqueous phase chemistry of transactinide elements

Toyoshima, Atsushi; Oe, Kazuhiro*; Asai, Masato; Attallah, M. F.*; Goto, Naoya*; Gupta, N. S.*; Haba, Hiromitsu*; Kaneko, Masashi*; Kaneya, Yusuke; Kasamatsu, Yoshitaka*; et al.

no journal, , 

Due to short half-lives less than 10 s and extremely low production rates, transactinide elements heavier than seaborgium (Sg) are produced on an atom per hour scale. Therefore, a continuous rapid chemistry assembly is required to study aqueous-phase chemistry of these heaviest elements. In the present study, we started developments of a continuous chemistry assembly. Our first attempt was made in on-line experiments with Mo and W, lighter homologs of Sg, to optimize a chemistry assembly consisting of a newly developed membrane degasser as an interface between gas-jet and aqueous phase, a flow electrolytic column apparatus utilized to control oxidation states of Mo and W ions, and the continuous liquid-liquid extraction apparatus of SISAK for separation. In the conference, present status of the developments will be presented.

18 (Records 1-18 displayed on this page)
  • 1