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Journal Articles

Information on ITER project, 52

Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 91(7), p.491 - 493, 2015/07

no abstracts in English

Journal Articles

Information on ITER project, 51

Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 91(5), p.368 - 370, 2015/05

no abstracts in English

Journal Articles

Information on ITER project, 50

Moriyama, Setsuko; Kajita, Shin*; Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 91(3), p.231 - 232, 2015/03

no abstracts in English

Journal Articles

Information on ITER project, 48

Moriyama, Setsuko; Ueno, Kenichi; Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 90(11), p.750 - 751, 2014/11

no abstracts in English

Journal Articles

Information on ITER Project, 47

Moriyama, Setsuko; Neyatani, Yuzuru; Ueno, Kenichi

Purazuma, Kaku Yugo Gakkai-Shi, 90(9), p.577 - 578, 2014/09

no abstracts in English

Journal Articles

Latest information on ITER Project, 46

Moriyama, Setsuko; Neyatani, Yuzuru; Ueno, Kenichi

Purazuma, Kaku Yugo Gakkai-Shi, 90(7), p.429 - 430, 2014/07

no abstracts in English

Journal Articles

RAMI analysis of the ITER central safety system

Kitazawa, Sin-iti; Okayama, Katsumi*; Neyatani, Yuzuru; Sagot, F.*; Van Houtte, D.*

Fusion Engineering and Design, 89(6), p.800 - 805, 2014/05

 Times Cited Count:1 Percentile:88(Nuclear Science & Technology)

In the ITER Project, the Reliability, Availability, Maintainability and Inspectability (RAMI) approach has been adopted for technical risk control to help aid the design of the components in preparation for operation and maintenance. A RAMI analysis was performed on the conceptual design of the ITER Central Safety System (CSS). A functional breakdown was prepared in a bottom-up approach. Reliability block diagrams were prepared to estimate the reliability and availability of each function under the stipulated operating conditions. The inherent availability of the ITER CSS expected after implementation of mitigation actions was calculated to be 99.80%, which is consistent with the project required value of 99.9 $$pm$$ 0.1%. A Failure Modes, Effects and Criticality Analysis was performed. This analysis reduces the risk levels and increases the availability of the main functions.

Journal Articles

Information on ITER Project, 45

Moriyama, Setsuko; Neyatani, Yuzuru; Inoue, Takashi

Purazuma, Kaku Yugo Gakkai-Shi, 90(5), p.307 - 308, 2014/05

no abstracts in English

Journal Articles

Information on ITER project, 44

Moriyama, Setsuko; Neyatani, Yuzuru; Ueno, Kenichi

Purazuma, Kaku Yugo Gakkai-Shi, 90(3), p.198 - 199, 2014/03

no abstracts in English

Journal Articles

RAMI analysis of the ITER CIS

Kitazawa, Sin-iti; Okayama, Katsumi*; Neyatani, Yuzuru; Sagot, F.*; Van Houtte, D.*

Fusion Engineering and Design, 89(2), p.88 - 93, 2014/02

 Times Cited Count:8 Percentile:33.97(Nuclear Science & Technology)

In the ITER project, the RAMI approach (Reliability, Availability, Maintainability and Inspectability) has been adopted for technical risk control to guide the design of components in preparation for operation and maintenance. RAMI analysis of the ITER Central Interlock System (CIS), which shall provide investment protection for the ITER systems, was performed on the conceptual design. A functional breakdown was prepared in a bottom-up approach, resulting in the system being divided into 5 main functions and 7 sub-functions which are described using the IDEF0 method. Reliability Block Diagrams were prepared to estimate the reliability and availability of each function under stipulated operating conditions. A Failure Modes, Effects and Criticality Analysis (FMECA) was performed to initiate risk mitigation action. The impact on the availability of the ITER CIS is small enough to comply with the availability requirement of the ITER project.

Journal Articles

Information on ITER project, 43

Moriyama, Setsuko; Neyatani, Yuzuru; Ueno, Kenichi

Purazuma, Kaku Yugo Gakkai-Shi, 90(1), p.86 - 87, 2014/01

no abstracts in English

Journal Articles

Information on ITER project, 42

Moriyama, Setsuko; Ueno, Kenichi; Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 89(11), p.820 - 821, 2013/11

no abstracts in English

Journal Articles

Information on ITER project, 41

Moriyama, Setsuko; Neyatani, Yuzuru; Ueno, Kenichi

Purazuma, Kaku Yugo Gakkai-Shi, 89(9), P. 637, 2013/09

no abstracts in English

Journal Articles

Information on ITER project, 40

Moriyama, Setsuko; Ueno, Kenichi; Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 89(7), p.509 - 510, 2013/07

no abstracts in English

Journal Articles

Information on ITER project, 39

Moriyama, Setsuko; Ueno, Kenichi; Neyatani, Yuzuru

Purazuma, Kaku Yugo Gakkai-Shi, 89(5), P. 328, 2013/05

no abstracts in English

Journal Articles

RAMI analysis of ITER CODAC

Kitazawa, Sin-iti; Okayama, Katsumi*; Neyatani, Yuzuru; Sagot, F.*; Van Houtte, D.*; Abadie, L.*; Yonekawa, Izuru*; Wallander, A.*; Klotz, W.-D.*

Fusion Engineering and Design, 87(7-8), p.1510 - 1513, 2012/08

 Times Cited Count:7 Percentile:42.93(Nuclear Science & Technology)

In the ITER project, Reliability, Availability, Maintainability and Inspectability (RAMI) approach has been adopted for technical risk control to guide the design of components and the preparation for operation and maintenance. RAMI analysis of the ITER CODAC system, the central plant control system, was performed in the current design available in conceptual design phase. A functional breakdown was prepared in a bottom-up approach, resulting in the system being divided into 5 main functions and sub-functions. Criticality matrices highlight the risks of the different failure modes with regard to their probability of occurrence and the impact on the availability. Reliability block diagrams were prepared to estimate the reliability and availability of each function under operating conditions. The inherent availability of the mandatory functions for the control of plasma experiments with mitigations was calculated to be 99.2% that is higher than the project required value of 98.8%.

Journal Articles

Engineering and maintenance studies of the ITER diagnostic upper port plug

Sato, Kazuyoshi; Omori, Junji; Kondoh, Takashi; Hatae, Takaki; Kajita, Shin*; Ishikawa, Masao; Neyatani, Yuzuru; Ebisawa, Katsuyuki*; Kusama, Yoshinori

Fusion Engineering and Design, 84(7-11), p.1713 - 1715, 2009/06

 Times Cited Count:1 Percentile:88.49(Nuclear Science & Technology)

Engineering analyses have been performed for the representative diagnostic upper port plug of ITER. Maintenance and integration design have been also carried out for the diagnostic components to be installed in the upper port plug. From the electromagnetic and structural analyses, it has come up an important problem to suppress the displacement of the upper port plug rather than to reduce the produced stress. Reducing the EM force will help to decrease the severity of potential displacement. Maximum displacement of the port plug decreases with increasing in the number of slits in a manner that the displacement would seem to be less than the design tolerance. A proposed low body roller and inner frame may enhance maintenance and integration. These studies and designs have established the design basis for the diagnostic upper port plug.

JAEA Reports

ITER technical term bilingual glossary year 2008 first half edition

Sato, Koichi; Seki, Fumiko*; Hasegawa, Shiori*; Sengoku, Akio; Kitazawa, Sin-iti; Neyatani, Yuzuru; Koizumi, Koichi

JAEA-Data/Code 2008-019, 43 Pages, 2008/09

JAEA-Data-Code-2008-019.pdf:1.17MB

On October 24th, 2007, the Agreement on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project (the "ITER Agreement") came into force, and Japan Atomic Energy Agency (JAEA) was appointed to a Domestic Agency (DA). The DA will contribute to the ITER construction in cooperation with ITER Organization (IO) where many ITER-specific technical terms and abbreviations were used. This book is a collection of those terms and abbreviations translated to Japanese.

Journal Articles

Development of ITER diagnostic upper port plug

Sato, Kazuyoshi; Omori, Junji; Ebisawa, Katsuyuki*; Kusama, Yoshinori; Neyatani, Yuzuru

Plasma and Fusion Research (Internet), 2, p.S1088_1 - S1088_4, 2007/11

A part of diagnostic device in vacuum vessel is planned to install in the port plug to make sure the line of sight of diagnostics. Only basic concept is shown for the port plug since design of diagnostic devices has not been substantiated yet. The integration design of the port plug has been performed and the structure concept for electro-magnetic and neutron load has been investigated as for the No.11 upper port plug to confirm reliability of the proposed design. Three diagnostics will be installed in the No.11 upper port plug, the edge Thomson scattering system, the visible-IR TV divertor viewing system and the neutron activation system. To integrate theses diagnostic systems in the port plug, it was designed the arrangement of the labyrinth of optical path, the driving mechanism and cooling systems for shutters and mirrors, the maintenance space. The part just behind the blanket shield module (BSM) was changed to secure a space for maintenance and for associated diagnostic first mirror and shutter, whereas this place is assigned for neutron shielding in the present design. The BSM support, which is main component to apply the electro-magnetic load, was arranged with optical path inside BSM.

JAEA Reports

Studies on representative disruption scenarios, associated electromagnetic and heat loads and operation window in ITER

Fujieda, Hirobumi; Sugihara, Masayoshi*; Shimada, Michiya; Gribov, Y.*; Ioki, Kimihiro*; Kawano, Yasunori; Khayrutdinov, R.*; Lukash, V.*; Omori, Junji; Neyatani, Yuzuru

JAEA-Research 2007-052, 115 Pages, 2007/07

JAEA-Research-2007-052.pdf:3.58MB

Impacts of plasma disruptions on ITER have been investigated to confirm the robustness of the design of the machine to the potential consequential loads. The loads include both electro-magnetic (EM) and heat on the in-vessel components and the vacuum vessel. Several representative disruption scenarios are specified. Disruption simulations with the DINA code and EM load analyses with a 3D finite element method code are performed for these scenarios. Some margins are confirmed in the EM load. Heat load on the first wall due to the vertical movement and the thermal quench (TQ) is calculated with a 2D heat conduction code. For vertical displacement event, beryllium ($$Be$$) wall will not melt during the vertical movement, prior to the TQ. Significant melting is anticipated for the upper $$Be$$ wall and tungsten baffle due to the TQ after the vertical movement. However, its impact could be mitigated by implementing a reliable detection system of the vertical movement and a mitigation system.

132 (Records 1-20 displayed on this page)