Zobrazeno 1 - 10
of 48
pro vyhledávání: '"Katsumi Ohsumi"'
Autor:
Yoshinori Chiba, Shunsuke Uchida, Takeshi Saitoh, Toshihiko Takahashi, Katsumi Ohsumi, Motohiro Aizawa
Publikováno v:
Journal of Nuclear Science and Technology. 39:1051-1059
Assessment of plant data and experiments on deposition of ion species on carbon steel were carried out in order to develop suitable countermeasures to reduce RHR (residual heat removal) piping dose rate. It was thought that radioactivity deposits on
Autor:
Hideyuki Hosokawa, Shunsuke Uchida, Motohiro Aizawa, Noboru Ishizawa, Yoshinori Chiba, Katsumi Ohsumi
Publikováno v:
Journal of Nuclear Science and Technology. 39:1041-1050
The dose rate of the residual heat removal (RHR) piping has been considered to be caused by accumulation of insoluble (crud) radioactive corrosion products on carbon steel surfaces. Soft shutdown procedures (i.e., plant shutdown with moderate coolant
Publikováno v:
Nuclear Technology. 133:92-102
A system has been developed for evaluating the effect of impurity intrusion on reactor water as part of the chemistry diagnostic system for boiling water reactor water. Past records of anomalous changes noted in reactor water quality were first surve
Publikováno v:
Journal of Nuclear Science and Technology. 36:805-817
In order to keep 60Co radioactivity low without incurring serious disadvantages regarding integrity of fuel cladding and reliability of structural materials, it is desirable to relate cooling water (especially 60Co behavior), structural materials and
Publikováno v:
Journal of Nuclear Science and Technology. 36:443-450
The elution rate of leachables from ion exchange resin, which is used in condensate demineralizers and is one of several major sources of organic compounds in BWR cooling water, was measured. Properties of the leachables and elution rate depended on
Autor:
Yoichi Wada, Naoto Shigenaka, Katsumi Ohsumi, Sakai Masanori, Kazuhiko Akamine, Shunsuke Uchida, Masahiko Tachibana
Publikováno v:
Journal of Nuclear Science and Technology. 35:301-308
In order to determine effects of hydrogen peroxide on stress corrosion cracking of structural materials in the primary cooling systems of boiling water reactors, a high temperature high pressure water loop with controlled hydrogen peroxide concentrat
Publikováno v:
Nuclear Technology. 110:250-257
Many efforts to preserve the structural integrity of major piping, components, and structures in a boiling water reactor (BWR) primary cooling system have been directed toward avoiding intergranular stress corrosion cracking (IGSCC). Application of h
Publikováno v:
Journal of Nuclear Science and Technology. 30:1001-1009
A method to detect small changes in water quality and diagnose their causes by analyzing on-line conductivity and pH data was proposed. Laboratory tests showed that effective noise reduction of measured on-line data could be got by using a median fil
Publikováno v:
Journal of Nuclear Science and Technology. 29:1120-1126
The concept of an advanced water chemistry diagnosis system for detection of anomalies and preventive maintenance of system components is proposed and put into a concrete form. Using the analogy to a medical inspection system, analyses of water chemi
Publikováno v:
Journal of Nuclear Science and Technology. 29:493-496