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Journal Articles

Role of micropores, mass transfer, and reaction rate in the hydrothermal alteration process of plagioclase in a granitic pluton

Yuguchi, Takashi*; Shobuzawa, Kaho*; Ogita, Yasuhiro*; Yagi, Koshi*; Ishibashi, Masayuki; Sasao, Eiji; Nishiyama, Tadao*

American Mineralogist, 104(4), p.536 - 556, 2019/04

 Times Cited Count:9 Percentile:76.14(Geochemistry & Geophysics)

This study describes the plagioclase alteration process with a focus on the role of micropores, mass transfer and reaction rate in the Toki granitic pluton, central Japan. The plagioclase alteration process involves albitization, K-feldspathization, and the formation of illite, calcite, fluorite and epidote. Such secondary minerals of hydrothermal origin in plagioclase within granitic rocks record the chemical characteristics of the hydrothermal fluid. Our results highlight (1) the nature of micropores such as distribution and volume in plagioclase, (2) the reaction nature of plagioclase alteration inferred by petrography and chemistry, (3) the physical conditions including alteration age and temperature, (4) the sequential variations of the fluid chemistry and (5) the mass transfer rate and reaction rate in the plagioclase alteration.

Journal Articles

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors, 4; Balance of plant

Chikazawa, Yoshitaka; Kato, Atsushi; Nabeshima, Kunihiko; Otaka, Masahiko; Uzawa, Masayuki*; Ikari, Risako*; Iwasaki, Mikinori*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05

Design study and evaluation for SDC and safety SDG on the BOP of the demonstration JSFR including fuel handling system, power supply system, component cooling water system, building arrangement are reported. For the fuel handling system, enhancement of storage cooling system has been investigated adding diversified cooling systems. For the power supply, existing emergency power supply system has been reinforced and alternative emergency power supply system is added. For the component cooling system and air conditioning, requirements and relation between safety grade components are investigated. Additionally for the component cooling system, design impact when adding decay heat removal system by sea water has been investigated. For reactor building, over view of evaluation on the external events and design policy for distributed arrangement is reported. Those design study and evaluation provides background information of SDC and SDG.

Journal Articles

Evaluation of external event effects on JSFR fuel handling system

Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Kaneko, Fumiaki*; Ide, Akihiro*

Nuclear Technology, 189(1), p.30 - 44, 2015/01

 Times Cited Count:1 Percentile:12.03(Nuclear Science & Technology)

Responding to the Fukushima Dai-ichi Nuclear Power Plant (1F-NPP) accident, robustness of the fuel handling system (FHS) in Japan sodium-cooled fast reactor (JSFR) against the earthquake and the tsunami is studied for 2010 design version. In the earthquake estimation, the margin of seismic resistance and the sloshing in Ex-vessel fuel storage tank (EVST) against the earthquake of the 1F-envelop condition was estimated. In terms of the tsunami evaluation, the scenario to lead fuel subassemblies into the stable cooling state and the potential of the cooling system are introduced in case of the loss of emergency power supply. As a result, it showed that JSFR FHS in the original design already had the potential to prevent the release of radioactive material. Additionally, some design improvements of the EVST cooling system was introduced.

Journal Articles

JSFR key technology evaluation on fuel handling system

Chikazawa, Yoshitaka; Kato, Atsushi; Obata, Hiroyuki*; Uzawa, Masayuki*; Koga, Kazuhiro*; Chishiro, Ryo*

Journal of Nuclear Science and Technology, 51(4), p.437 - 447, 2014/04

 Times Cited Count:1 Percentile:10.7(Nuclear Science & Technology)

A simplified fuel handling system design for the demonstration JSFR has been proposed. FaCT phase I results of key technology evaluations on a pantograph fuel handling machine, a fuel transfer pot with two core component positions, dry spent fuel cleaning and minor actinide-bearing fresh fuel shipping cask are being developed. Experimental and analytical efforts have shown that key technologies to develop simplified fuel handling system are matured enough to proceed large scale sodium experiments and conceptual design study for the demonstration JSFR.

Journal Articles

Progress of design study on fuel handling system in JSFR against design extension conditions

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Ide, Akihiro*; Kaneko, Fumiaki*; Hara, Hiroyuki*

Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.607 - 615, 2014/04

Responding to the TEPCO's Fukushima Dai-ichi Nuclear Power Station accident, the design study was carried out to enhance cooling function of fuel handling system for Japan sodium-cooled fast reactor (JSFR). Design measures to maintain an FHS cooling function even in case of Design Extension Conditions are studied; such as alternative cooling systems which are independent and diversified from design basis cooling systems. Based on effectiveness evaluations, it was confirmed that these measures have adequate availability against the postulated design extension conditions.

Journal Articles

Evaluation and improvement on external-hazard proof of JSFR fuel handling system

Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*

Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.475 - 482, 2012/06

Responding to the Fukushima Dai-ichi Nuclear Power Plant (1F-NPP) accident, the earthquake and the tsunami proof of the fuel handling system (FHS) in Japan Sodium-cooled Fast Reactor (JSFR) is studied. In the earthquake proof estimation, the margin of seismic resistance against the earthquake of the 1F-envelop condition and the sloshing behavior in the EVST is estimated. In terms of the tsunami proof, the scenario to lead fuel subassemblies into the stable cooling state and the potential of the cooling system is introduced in case of loss of the emergency power supply. As a result, it is clear that JSFR FHS originally could already be prepared to have the potential to prevent the release of radioactive material.

Journal Articles

Comparison of sodium-cooled reactor fuel-handling systems with and without an ex-vessel storage tank

Chikazawa, Yoshitaka; Uzawa, Masayuki*; Usui, Shinichi*; Tozawa, Katsuhiro*; Kotake, Shoji

Nuclear Technology, 177(3), p.293 - 302, 2012/03

 Times Cited Count:3 Percentile:28.72(Nuclear Science & Technology)

JSFR is a concept of a commercial sodium-cooled fast reactor which has been being studied in Fast Reactor Cycle Technology Development (FaCT) project since 2006. For the JSFR fuel handling, various fuel handling systems (FHSs) were investigated and an advanced FHS with an ex-vessel storage tank (EVST) has been selected. The other FHS concepts investigated are evolutional FHSs without an EVST. The result has indicated that the construction cost of the evolutional systems do not reduce the construction cost dramatically, which is mainly due to additional safety measures required higher decay heat handling in gas atmosphere and due to the necessity of separated fresh and failed fuel storage. From an economical point of view, a longer plant outage of the evolutional systems offsets its advantage of the lower construction cost. On the basis of the results of this comparative study, JSFR has selected the FHS with an EVST.

Journal Articles

In-service inspection and repair program for commercialized sodium-cooled fast reactor

Nishiyama, Noboru; Kotake, Shoji*; Uzawa, Masayuki*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 9 Pages, 2012/00

Japan Sodium-cooled Fast Reactor (JSFR) adopts a compact design to reduce construction cost as a commercialized reactor. A commercialized fast reactor is also expected to be excellent in operation and maintenance for high availability. From the study for JSFR, in-service inspection and repair program necessary for JSFR has been developed. Major component design has been improved considering ISI accommodation, and the required ISI devices have been specified according to the proposed ISI program. To increase maintainability of JSFR, such approaches are employed at the conceptual design stage.

Journal Articles

Conceptual design study for the demonstration reactor of JSFR, 6; Fuel handling system design

Chikazawa, Yoshitaka; Kato, Atsushi; Obata, Hiroyuki*; Nishiyama, Noboru; Uzawa, Masayuki*; Tozawa, Katsuhiro*; Chishiro, Ryo*

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10

A preliminary design of the JSFR fuel handling system has been proposed. FaCT phase I results of key technology evaluations on preliminary safety assessment, a pantograph fuel handling machine, a sodium pot with two core component positions, dry spent fuel cleaning and minor actinide-bearing fresh fuel shipping cask are provided.

Journal Articles

Particle transport of LHD

Tanaka, Kenji*; Kawahata, Kazuo*; Tokuzawa, Tokihiko*; Akiyama, Tsuyoshi*; Yokoyama, Masayuki*; Shoji, Mamoru*; Michael, C. A.*; Vyacheslavov, L. N.*; Murakami, Sadayoshi*; Wakasa, Arimitsu*; et al.

Fusion Science and Technology, 58(1), p.70 - 90, 2010/07

 Times Cited Count:17 Percentile:78.18(Nuclear Science & Technology)

Particle confinement processes were studied in detail on LHD. Diffusion coefficients (D) and convection velocities (V) were estimated from density modulation experiments. The magnetic configuration and collisionality were widely scanned in order to investigate parameter dependences of D and V. In order to study the effect of the magnetic configuration, magnetic axis positions (R$$_{ax}$$) were scanned from 3.5 m to 3.9 m. This scan changed the magnetic ripples quite significantly, enabling the effects of neoclassical properties on measured values to be widely elucidated. Dependences of electron temperature (T$$_{e}$$) and helically trapped normalized collsionality ($$nu$$$$_{h}^{*}$$), where $$nu$$$$_{h}^{*}$$=1 indicates a rough boundary between the 1/$$nu$$ and plateau regimes, were examined using the heating power scan of neutral beam injection (NBI). It was found out that generally larger (or smaller) contributions of neoclassical transport resulted in more hollow (or peaked) density profiles. The larger neoclassical contribution was found to be situated at a more outwardly shifted R$$_{ax}$$ for the same T$$_{e}$$, and higher T$$_{e}$$ or lower $$nu$$$$_{h}^{*}$$ at each R$$_{ax}$$. However, it is to be noted that R$$_{ax}$$=3.5 m showed different characteristics from these trends in that this case showed a more peaked density profile at higher T$$_{e}$$.

Journal Articles

Comparative study on advanced fuel handling systems for JSFR

Chikazawa, Yoshitaka; Uzawa, Masayuki*; Usui, Shinichi*; Tozawa, Katsuhiro*; Kotake, Shoji

Proceedings of 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10) (CD-ROM), p.10142_1 - 10142_9, 2010/06

Journal Articles

Development of the JSFR fuel handling system and mockup experiments of fuel handling machine in abnormal conditions

Kato, Atsushi; Hirata, Shingo; Chikazawa, Yoshitaka; Uto, Nariaki; Obata, Hiroyuki*; Kotake, Shoji*; Uzawa, Masayuki*

Proceedings of 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10) (CD-ROM), p.692 - 699, 2010/06

In the JSFR design, a single rotating plug and an upper inner structure (UIS) with a vertically penetrating slit are proposed, so that the fuel handling machine (FHM) can access any subassembly by horizontal movement of the FHM arm in the slit space. As a result of a full-scale mockup test, excellent performance in normal operation has been shown. In this study, from the viewpoint of achieving reliability of the pantograph type FHM, behavior of the FHM mockup have been investigated under abnormal conditions.

Journal Articles

Experimental investigation of particle pinch associated with turbulence in LHD heliotron and JT-60U tokamak plasmas

Tanaka, Kenji*; Takenaga, Hidenobu; Muraoka, Katsunori*; Michael, C.*; Vyacheslavov, L. N.*; Yokoyama, Masayuki*; Yamada, Hiroshi*; Oyama, Naoyuki; Urano, Hajime; Kamada, Yutaka; et al.

Proceedings of 22nd IAEA Fusion Energy Conference (FEC 2008) (CD-ROM), 8 Pages, 2008/10

Comparative studies were carried out in LHD heliotron and JT-60U tokamak plasmas to elucidate the most essential parameter(s) for control of density profiles in toroidal systems. A difference in the collisionality dependence was found between the two devices. In LHD, the density peaking factor decreased with decrease of the collisionality at the magnetic axis position (R$$_{rm au}$$) 3.6 m, while the density peaking factor gradually increased with a decreased of collisionality at R$$_{rm au}$$ = 3.5 m. On the other hand, in JT-60U, the density peaking factor clearly increased with a decrease of the collisionality. The difference in the collisionality dependence between R$$_{rm au}$$ = 3.5 and R$$_{rm au}$$ = 3.6 m is likely due to the contribution of the anomalous transport. At R$$_{rm au}$$ = 3.5 m, larger anomalous transport caused a similar collisionality dependence. Change of the fluctuation property was observed with different density profiles in the plasma core region on both devices. In JT-60U, the increase of the radial coherence was observed with higher density peaking profile suggesting enhanced diffusion and inward directed pinch. For a magnetic axis positions (R$$_{rm au}$$) at 3.6 m in LHD, the increase of the fluctuation power with an increase in P$$_{rm NB}$$ was observed for a hollow density profile suggesting an increase on diffusion due to anomalous processes. Change of density profiles from peaked to hollow indicates change in the convection direction. This is due to increase in neoclassical processes. The reduction of the density peaking factor with increase of P$$_{rm NB}$$ in LHD is partly due to the neoclassical effect and partly due to the anomalous effect.

Journal Articles

Effect of cation on HTO/H$$_{2}$$O separation and dehydration characteristics of Y-type zeolite adsorbent

Iwai, Yasunori; Uzawa, Masayuki*; Yamanishi, Toshihiko

Fusion Science and Technology, 54(2), p.462 - 465, 2008/08

 Times Cited Count:4 Percentile:31.93(Nuclear Science & Technology)

Adsorber has been studied to apply in the first stage of water detritiation system processing more than 100 kg/h of high-level tritiated water generated in a future fusion plant. Zeolite is a suitable adsorbent since it is an inorganic matter having a large water capacity. Rapid dehydration characteristic as well as large HTO/H$$_{2}$$O separation factor is necessary for adsorber to minimize its size. Present experiments were focused on the effect of cation on HTO/H$$_{2}$$O separation and dehydration characteristics of Y-type zeolites. It was found that the isotope separation factors are around 1.1-1.2 under static conditions. As for dehydration, operating temperature fixs the movable water capacity of the zeolites and the capacity at room temperature is NaY $$>$$ CaY $$>$$ KY. HTO dehydration characteristics depend on the accumulated purge gas amount and the purge gas rate is less influential. It is found that pressure swing is an effective method for HTO dehydration.

Journal Articles

Particle transport and fluctuation characteristics around the neoclassically optimized configurations in LHD

Tanaka, Kenji*; Michael, C.*; Vyacheslavov, L. N.*; Yokoyama, Masayuki*; Murakami, Sadayoshi*; Wakasa, Arimitsu*; Takenaga, Hidenobu; Muraoka, Katsunori*; Kawahata, Kazuo*; Tokuzawa, Tokihiko*; et al.

Plasma and Fusion Research (Internet), 3, p.S1069_1 - S1069_7, 2008/08

Density profiles in LHD were measured and particle transport coefficients were estimated from density modulation experiments in LHD. The dataset of different magnetic axis, toroidal magnetic filed and heating power provided data set of widely scanned neoclassical transport. At minimized neoclassical transport configuration ($$R$$$$_{rm ax}$$ = 3.5 m, $$B$$$$_{rm t}$$ = 2.8 T) showed peaked density profile. Its peaking factor increased gradually with decrease of collisional frequency. This is a similar result observed in JT-60U. At other configuration, peaking factor reduced with decrease of collsional frequency. Data set showed that larger contribution of neoclassical transport produced hollowed density profile. Comparison between neoclassical and estimated particle diffusivity showed different minimum condition. Clear difference of spatial profile of turbulence was observed between hollowed and peaked density profiles. Major part of fluctuation existed in the unstable region of ion temperature gradient mode.

Journal Articles

Comparisons of density profiles in JT-60U tokamak and LHD helical plasmas with low collisionality

Takenaga, Hidenobu; Tanaka, Kenji*; Muraoka, Katsunori*; Urano, Hajime; Oyama, Naoyuki; Kamada, Yutaka; Yokoyama, Masayuki*; Yamada, Hiroshi*; Tokuzawa, Tokihiko*; Yamada, Ichihiro*

Nuclear Fusion, 48(7), p.075004_1 - 075004_11, 2008/07

 Times Cited Count:28 Percentile:73.66(Physics, Fluids & Plasmas)

In order to understand particle transport systematically in toroidal plasmas, electron density profiles were compared in JT-60U tokamak and LHD helical plasmas with low collisionality. Peakedness of density profiles increased with decreasing collisionality in ELMy H-mode plasmas of JT-60U, when the collisionality at half the minor radius was in the collisionless regime. Collisionality dependence of density profiles in LHD plasmas was similar to that in JT-60U plasmas in the same collisionality regime, when neoclassical transport was suppressed by geometrical optimization. On the other hand, in the LHD plasmas having relatively larger neoclassical transport than that in the above case, peakedness of density profiles decreased with decreasing collisionality. Neoclassical transport enhanced by the non-axisymmetric effect significantly affected density profiles with low collisionality in LHD plasmas. Density profiles in LHD plasmas tended to approach those in JT-60U, which are dominated by anomalous transport, as the contribution of neoclassical transport was reduced.

Journal Articles

Studies on the behavior of tritium in components and structure materials of tritium confinement and detritiation systems of ITER

Kobayashi, Kazuhiro; Isobe, Kanetsugu; Iwai, Yasunori; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Miura, Hidenori*; et al.

Nuclear Fusion, 47(12), p.1645 - 1651, 2007/12

 Times Cited Count:3 Percentile:12.38(Physics, Fluids & Plasmas)

The confinement and removal of tritium are the key subjects for safety of ITER. The ITER buildings are confinement barriers of tritium. In a hot cell building, tritium is often released, as vapor and is in contact with the inner walls. Also those of an ITER tritium plant building will be exposed to tritium in an accident. However, the data are scarce, especially on the penetration of tritium into the concrete of the wall materials. The tritium released in the buildings is removed by the Atmosphere Detritiation Systems (ADS), where the tritium is oxidized by catalysts and is removed as water. Special gas of SF$$_{6}$$ is used in ITER, and is expected to be released in an accident such as fire. Although the SF$$_{6}$$ gas has the potential as a catalyst poison, the performance of ADS with the existence of SF$$_{6}$$ has not been confirmed yet. Tritiated water is produced in the regeneration process of ADS, and is subsequently processed by the ITER Water Detritiation System (WDS). One of the key components of WDS is an electrolysis cell. The electrolysis cell is made of organic compounds, and there is no data on the durability of the cell exposed to tritium. To overcome these issues in a global tritium confinement, a series of experimental studies have been carried out as an ITER R&D task: (1) tritium behavior in concrete; (2) effect of SF$$_{6}$$ on performance of ADS; and (3) tritium durability of electrolysis cell of ITER-WDS.

Journal Articles

Development of ceramic electrolysis method for processing high-level tritiated water

Isobe, Kanetsugu; Uzawa, Masayuki*; Yamanishi, Toshihiko; Kurita, Koichi*

STI/PUB/1284 (CD-ROM), 7 Pages, 2007/04

The high-level tritium water is expected to be produced in the vacuum chamber and in a breeding blanket system. It is one of the key issues to recover tritium from the high-level tritium water from the viewpoint of tritium inventory control in the vacuum vessel as well as tritium recover as a fuel. A solid polymer electrolysis used in WDS (Water Detiritiation System) of ITER can not be applied for the high-level tritium water to avoid the radiation damage. A ceramic electrolysis would be only a method to recover tritium from the high-level tritium water. The water is decomposed by the reduction on the electrode in the electrolysis. Aiming to increase the efficiency of this process, we have developed effective electrode, such as platinum and yttria stabilized zirconia (Pt-YSZ) compound. In this study, we developed new two types of electrode containing cerium oxide (Ceria). One electrode has a double-layer structure used ceria as an inner layer and Pt-YSZ as an outer layer. The other electrode used the ceria as an additive element of Pt-YSZ electrode. Both electrodes show a higher performance than that of Pt-YSZ. Especially, the double layer electrode shows three times higher efficiency than that of Pt-YSZ electrode. In the comparison between Pt-YSZ electrode and the new electrodes, the characteristics of both the electrodes, such as impedance and a structure, were also studied.

Journal Articles

Studies on behavior of tritium in components and structure materials of tritium confinement and detritiation systems of ITER

Kobayashi, Kazuhiro; Isobe, Kanetsugu; Iwai, Yasunori; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Miura, Hidenori*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

no abstracts in English

Journal Articles

Progress in microwave diagnostics and physics issues in magnetically confined plasmas

Mase, Atsushi*; Kogi, Yuichiro*; Hojo, Hitoshi*; Yoshikawa, Masayuki*; Itakura, Akiyoshi*; Chujo, T.*; Tokuzawa, Tokihiko*; Kawahata, Kazuo*; Nagayama, Yoshio*; Oyama, Naoyuki; et al.

Fusion Science and Technology, 51(2T), p.52 - 57, 2007/02

 Times Cited Count:3 Percentile:26.87(Nuclear Science & Technology)

no abstracts in English

39 (Records 1-20 displayed on this page)