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Journal Articles

Consideration of 3D laser scanning and verification techniques for as-built modeling in nuclear fuel cycle facilities

Okubo, Naoto; Ogawa, Tsuyoshi; Asada, Mamoru*; Fukushima, Manabu*; Nakajima, Yuko*; Terunuma, Hiroaki*; Takaya, Akikazu; Nakazaki, Katsutoshi; Yamamoto, Masahiko

Nihon Hozen Gakkai Dai-21-Kai Gakujutsu Koenkai Yoshishu, 4 Pages, 2025/07

Application of 3D laser scanning for as-built modeling has recently attracted increasing attention. This study investigates scanning techniques suitable for complex environments such as nuclear fuel cycle facilities. These facilities commonly use stainless steel components, which highly reflect optical laser scanning and features complicated arrange of piping and equipment. To ensure data accuracy under such challenging conditions, techniques including multi-angle scanning and noise reduction were employed. The obtained data were compared with facility's original design data. The results indicated that the proposed approach enables high-quality data acquisition and facilitates the generation of accurate 3D point cloud data, even in geometrically and optically complex environments. The resulting 3D point cloud data contribute to a comprehensive understanding of facilities and are expected to support work planning processes throughout facility decommissioning.

JAEA Reports

Fracture toughness of Zr-2.5wt%N6 pressure tubes

Asada, Takashi; Honda, Shunichi*; Takeuchi, Mamoru*

PNC TN341 83-11, 16 Pages, 1983/02

PNC-TN341-83-11.pdf:4.44MB

Measurements of fracture toughness of HT Zr-2.5wt% Nb pressure tubes have been made by study ing internally pressurizing(burst) test specimens and small bending test specimens. These tests were conducted from a viewpoint of the effects of hydrogencontent, hydrideorientation, temperature and crack configuration on the fracture toughness Kc. Results of the experiments showed that Kc decreased with increasing hydrogen content, but it wouid be little affected by hydrogen content at reactor operating temperature. The value of Kc could be quantitatively evaluated by RHC defined by radial hydride content (RHC) perpendicular to the tensile stress, and it decreased with increasing RHC.

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