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FBR Safety Unit
JAEA-Research 2011-044, 185 Pages, 2012/02
JAEA-Research-2011-044.pdf:12.52MB
JAEA has been developing a flow-induced vibration methodology applied to the JSFR piping under the FaCT project. As part of this development, flow pattern in the single-elbow pipe has been investigated with the measurement of fluid force induced by turbulence flow and of the flow-induced vibration response. The experimental results have served to the development and vibration of the flow-induced vibration evaluation methodology. Based on these outcomes, JAEA has established a working group on a guideline of large-diameter piping flow-induced vibration evaluation under the JAEA's Thermal-Hydraulic Research Committee for creating the JAEA internal guideline. The first proposal of the guideline was summarized from the achievements of the working group activity. Since technical discussion has been made deeply in developing the guideline, this report summarizes technical background and understanding for the guideline.
FBR Safety Unit
JAEA-Research 2011-021, 35 Pages, 2011/09
JAEA-Research-2011-021.pdf:2.27MB
JAEA has been developing a flow-induced vibration methodology applied to the JSFR piping under the FaCT project. As part of this development, flow pattern in the single-elbow pipe has been investigated with the measurement of fluid force induced by turbulence flow and of the flow-induced vibration response. The experimental results have served to the development and vibration of the flow-induced vibration evaluation methodology. Based on these outcomes, JAEA has established a working group on a guideline of large-diameter piping flow-induced vibration evaluation under the JAEA's Thermal-Hydraulic Research Committee for creating the guideline. This report is a first proposal of the guideline from the achievements of the working group activity.
FBR Safety Unit
JAEA-Review 2011-032, 207 Pages, 2011/06
JAEA-Review-2011-032.pdf:5.39MB
Japan Atomic Energy Agency (JAEA) is conducting the FaCT (Fast Reactor Cycle Technology Development) project in cooperation with Japan Atomic Power Company (JAPC) and Mitsubishi FBR systems inc. (MFBR), where an advanced loop-type fast reactor named JSFR (Japan Sodium-cooled Fast Reactor) is being developed. It is important to develop software technologies (a safety guideline, safety design criteria, safety design standards etc.) of FBRs as well as hardware ones (a reactor plant itself) in order to address prospective worldwide utilization of FBR technology. Therefore, it is expected to establish a rational safety guideline applicable to the JSFR and harmonized with national nuclear-safety regulations as well, including Japan, the United States and the European Union. This report presents domestic and international status of safety guideline development for sodium-cooled fast reactors (SFRs), results of comparative study for safety requirements provided in existing documents and a proposal for safety requirements of future SFRs with a roadmap for their refinement and worldwide utilization.
FBR System Engineering Unit; FBR Systems Reliability Research Unit; FBR Safety & Innovative Technology Unit; FBR Cycle Synthesis Unit; Innovative Water Reactor Design Group; Nuclear Science and Engineering Directorate
JAEA-Research 2006-042, 36 Pages, 2006/06
JAEA-Research-2006-042.pdf:2.34MBJAEA-Research-2006-042-Incl(CD).pdf:84.0MB
no abstracts in English