Search Results - "Furusawa, Takayuki"
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Improving the safety of the high temperature gas-cooled reactor ‘HTTR’ based on Japan’s new regulatory requirements
Published in Nuclear engineering and design (01-03-2022)“…•The HTTR license has been re-licensed to meet the new regulatory requirements in Japan.•Simple measures can protect the facility's safety against…”
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Development of the maintenance technologies for the future high-temperature gas cooled reactor (HTGR) using operating experiences acquired in high-temperature engineering test reactor (HTTR)
Published in Journal of nuclear science and technology (02-12-2014)“…This paper describes the lessons learned of the maintenance technologies, which have been and will be developed by using the high-temperature engineering test…”
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Investigation on dust captured by quintuple filters installed upstream of primary gas circulators in HTTR
Published in Journal of nuclear science and technology (02-12-2014)“…A main objective to install filters upstream of primary gas circulators in the high temperature engineering test reactor (HTTR), besides having a primary…”
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Investigation of chemical characteristics of primary helium gas coolant of HTTR (high temperature engineering test reactor)
Published in Nuclear engineering and design (01-05-2014)“…The technical basis of helium gas purification control for HTGRs was established by verifying the design of the Primary Helium Purification System (PHPS) of…”
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Operation and maintenance experience from the HTTR database
Published in Journal of nuclear science and technology (02-12-2014)“…The Japan Atomic Energy Agency has been establishing a database of operation and maintenance experience for the High Temperature Engineering Test Reactor. The…”
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Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)
Published in Nuclear engineering and design (01-05-2014)“…To establish the technical basis of HTGR (High Temperature Gas cooled Reactor), the long term high temperature operation using HTTR was carried out in the high…”
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Short design descriptions of other systems of the HTTR
Published in Nuclear engineering and design (01-10-2004)“…The HTTR mainly consists of the core components, reactor pressure vessel, cooling systems, instrumentation and control systems, and containment structures. The…”
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Cooling system design and structural integrity evaluation
Published in Nuclear engineering and design (01-10-2004)“…The high temperature engineering test reactor (HTTR), which is the first high temperature gas-cooled reactor (HTGR) in Japan, is a test reactor with a thermal…”
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Short design descriptions of other systems of the HTTR: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs
Published in Nuclear engineering and design (2004)Get full text
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Cooling system design and structural integrity evaluation: Japan's HTTR. Japan's first High Temperature Engineering Test Reactor of JAERI, its design, its components, its safety features, its planned experiments and its industrial applications, including Japan's concept of future HTRs
Published in Nuclear engineering and design (2004)Get full text
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Plan for first phase of safety demonstration tests of the High Temperature Engineering Test Reactor (HTTR)
Published in Nuclear engineering and design (01-09-2003)“…Safety demonstration tests using the High Temperature Engineering Test Reactor (HTTR) will be conducted for the purpose of demonstrating inherent safety…”
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Inspection techniques for primary pressurized water cooler tubes in the high temperature engineering test reactor
Published in Nuclear engineering and design (01-08-2002)“…A primary pressurized water cooler (PPWC) with 136 inverse-U-tubes is installed in the primary cooling system of the high temperature engineering test reactor…”
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