3件が見つかりました。
論文
DPマッチング，周波数領域のヒストグラム及び主成分分析法を用いたインバータ制御回転機械の自動診断法
著者:
小林 祐介,Yusuke KOBAYASHI,富田 優,Masaru TOMITA,宋 瀏陽,Liuyang SONG,陳山 鵬,Ho JINYAMA
発刊日:
公開日:
キーワードタグ:
Automatic Diagnosis DP Matching Frequency Change Histogram of Frequency Domain Inverter Control Multi-band Filter Principal Component Analysis Statistical Filter
小林 祐介,Yusuke KOBAYASHI,富田 優,Masaru TOMITA,宋 瀏陽,Liuyang SONG,陳山 鵬,Ho JINYAMA
発刊日:
公開日:
キーワードタグ:
Automatic Diagnosis DP Matching Frequency Change Histogram of Frequency Domain Inverter Control Multi-band Filter Principal Component Analysis Statistical Filter
In recent years, inverter controlled rotating machines are becoming major for saving energy and maintenance labor. Up to now many kinds of methods about diagnosing rotating machines are proposed, but most of them are applicable only for machines rotating at constant speed. When rotating speed change, the acceleration signal measured for diagnosis becomes quite different. And applying the reviously proposed methods to invertercontrolled machines is difficult. So, in this paper, the method in which the diagno...
英字タイトル:
Automatic Diagnosis Method for Inverter Controlled Rotating Machinery Using DP Matching, Histogram of Frequency Domain and Principal Component Analysis
英字タイトル:
Automatic Diagnosis Method for Inverter Controlled Rotating Machinery Using DP Matching, Histogram of Frequency Domain and Principal Component Analysis
論文
先進的なナトリウム冷却高速炉の炉心出口部における サーマルストライピング現象に関する水流動試験 (1)制御棒周辺部の温度変動緩和対策の提案
著者:
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
A design study of an advanced sodium-cooled fast reactor (Advanced-SFR) has been conducted in Japan Atomic Energy Agency (JAEA). Hot sodium from the fuel assembly can mix with cold sodium from the control rod (CR) channel and the blanket assemblies at the bottom plate of the Upper Internal Structure (UIS). Temperature fluctuation due to mixing of the fluids at different temperature between the core outlet and cold channel may cause high cycle thermal fatigue on the structure around the bottom of UIS. A wate...
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of an Advanced Sodium-cooled Fast Reactor? (1) Proposal of Countermeasures to Mitigate Temperature Fluctuations around Control Rods?
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of an Advanced Sodium-cooled Fast Reactor? (1) Proposal of Countermeasures to Mitigate Temperature Fluctuations around Control Rods?
論文
先進的なナトリウム冷却高速炉の炉心出口部における サーマルストライピング現象に関する水流動試験 (2)径方向ブランケット燃料集合体周辺部の 温度変動緩和対策の提案
著者:
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
小林 順,Jun KOBAYASHI,相澤 康介,Kosuke AIZAWA,江連 俊樹,Toshiki EZURE,栗原 成計,Akikazu KURIHARA,田中 正暁,Masaaki TANAKA
発刊日:
公開日:
キーワードタグ:
High Cycle Thermal Fatigue Particle Image Velocimetry Sodium-cooled Fast Reactor Thermal Striping Upper Internal Structure
Focusing on the thermal striping phenomena that occurs at a bottom of the internal structure of an advanced sodium-cooled fast reactor (Advanced-SFR) that has been designed by the Japan Atomic Energy Agency, a water experiment using a 1/3 scale 60 degree sector model simulating the upper plenum of the Advanced-SFR has been conducted to examine countermeasures for the significant temperature fluctuation generated around the bottom of Upper Internal Structure (UIS). In the previous paper, we reported the effe...
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of?an Advanced Sodium-cooled Fast Reactor? (2) Proposal of Countermeasures to Mitigate Temperature Fluctuations?around Radial Blanket Fuel Assemblies?
英字タイトル:
Water Experiments on Thermal Striping Phenomena at the Core Outlet of?an Advanced Sodium-cooled Fast Reactor? (2) Proposal of Countermeasures to Mitigate Temperature Fluctuations?around Radial Blanket Fuel Assemblies?