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Ito, Hideaki; Maeda, Shigetaka; Naito, Hiroyuki; Akiyama, Yoichi; Miyamoto, Kazuyuki; Ashida, Takashi; Noguchi, Koichi; Ito, Chikara; Aoyama, Takafumi
JAEA-Technology 2010-049, 129 Pages, 2011/03
The in-vessel gamma dose rate was measured in the experimental fast reactor Joyo to evaluate the activation of reactor structural components and the radiation exposure of the fiber scope used for in-vessel visual inspection. The measurement system, which requires a wide sensitivity range and high durability in a high-temperature environment, was specifically developed for use in the sodium cooled fast reactor. Using this system, the in-vessel gamma dose rate with cooling times of 450 and 720 days after reactor shutdown was measured in Joyo, which has been operated for 71,000 hours over approximately 30 years. The gamma dose rate was calculated using QAD-CGGP2 code with the gamma source intensity obtained by the ORIGEN2 code. The neutron flux used as input to the ORIGEN2 was evaluated by the Joyo dosimetry method. The ratio between the calculated and experimental values ranged from 1.1 to 2.4, confirming the accuracy of gamma dose rate and component activation calculation.
Kanematsu, Manabu*; Maruyama, Ippei*; Noguchi, Takafumi*; Iikura, Hiroshi; Tsuchiya, Naoko*
Nuclear Instruments and Methods in Physics Research A, 605(1-2), p.154 - 158, 2009/06
Times Cited Count:70 Percentile:97.52(Instruments & Instrumentation)Maruyama, Ippei*; Kanematsu, Manabu*; Noguchi, Takafumi*; Iikura, Hiroshi; Teramoto, Atsushi*; Hayano, Hiroyuki*
Nuclear Instruments and Methods in Physics Research A, 605(1-2), p.159 - 162, 2009/06
Times Cited Count:32 Percentile:88.45(Instruments & Instrumentation)Kanematsu, Manabu*; Noguchi, Takafumi*; Maruyama, Ippei*; Iikura, Hiroshi
Konkurito Kogaku Nenji Rombunshu (DVD-ROM), 29(1), p.981 - 986, 2007/00
Neutron radiography is one of the non-destructive methods. In this research, neutron radiography was applied to visualize and quantify the water penetration into concrete through cracks. The radiographs were obtained by the TNRF (Thermal Neutron Radiography Facility) installed at a research reactor, JRR-3M, in the Japan Atomic Energy Agency (JAEA). The quantitative capability of neutron radiography for the water content and the penetration depth in cement paste specimen were confirmed. The effects of crack and water content on the velocity and the depth of water penetration into concrete were visualized with several concrete specimens, to which surface water was supplied through the container.
Tsuchiya, Naoko*; Kanematsu, Manabu*; Noguchi, Takafumi*; Iikura, Hiroshi
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