BWR owners and plant fabricators have been making efforts to decrease the ISI parts where UT is difficult to be conducted. For that purpose, UT verification test for both detection and sizing qualification through deposit of pipe weld joint started in 2009 and will last until 2011. In 2009, UT verification test for stainless steel pipe weld joint has been performed. Test samples are stainless steel pipes with welds and sizes are 600A.350A.150A with EDM notches and/or SCC cracks. Angle beam methods and...
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit

BWR owners and plant fabricators have been making efforts to decrease the ISI parts where UT is difficult to be cond ucted. For that purpose, UT verification test for both detection and sizing qualification through deposit of pipe wel d joint started in 2009 and will last until 2011. In 2009, UT verification test for stainless steel pipe weld joint has been performed. Test samples are stainless steel pipes with welds and sizes are 600A.350A.150A with EDM notches a nd/or SCCs. Angle beam methods and phased...
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit

As nuclear power plants age, the importance of maintenance increases and there is a need to apply inspection technologies suitable to importance of each item of equipment. In boiling water reactors, advanced inspection technologies are expected for internal components, i.e. shroud supports with complex-shaped Ni-based alloy welds. As an inspection technology for field inspection of the shroud supports phased array technology has been mainly developed for sizing of Stress Corrosion Crackings accessed from ...
英字タイトル:
Ultrasonic testing techniques for inspection of BWR internal components welds.

地震を受けた機器における塑性ひずみ検出方法の適用について 米谷 豊,Yutaka KOMETANI,伊東 敬,Takashi ITO,野中 善夫,Yoshio NONAKA,高木 愛夫,Yoshio TAKAGI,黒崎 裕一,Yuichi KUROSAKI,羽鳥 正訓,Yoshio TAKAGI, １．はじめに東京電力株式会社　柏崎刈羽原子力発電所は、2007年7月16日に発生した中越沖地震により被災したが、原子炉は安全に停止するとともに、耐震設計グレードの高い機器では外見上の損傷は認められなかった。ま......

The decommissioning work at Fukushima Daiichi Nuclear Power Station needs to plan based on the information of investigation in the reactor building and the environmental status such as radiation dose rate. It is necessary to develop the remote operation technologies for investigation in the reactor building, radiation measurement, removal of spent fuel and fuel debris. Hitachi Group is developing the various remote operation technologies for removal of spent fuels from the spent fuel pool and fuel debr...
英字タイトル:
Development of technology for fuel removal of the Fukushima Decommissioning

Since the accident at Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company, reconstruction work at Fukushima has needed to deal with high radiation environments and has demanded new technologies. This requires the development of remote-controlled robots capable of rubble removal, radiation measurement, and other technologies, as well as ways of utilizing these technologies in tandem. It is also necessary to conduct a site survey (including the visual assessment, identification of...
英字タイトル:
Development of remote-controlled robot technology for the Fukushima Reconstruction