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Featured researches published by Masaaki Tanaka.


ASME 2002 Pressure Vessels and Piping Conference | 2002

Evaluation of Thermal Stress Ratchet in Plastic FEA

Yukinori Yamamoto; Norimichi Yamashita; Masaaki Tanaka

Alternative stress evaluation criteria suitable for Finite Element Analysis (FEA) proposed by Okamoto et al. [1] have been studied by the Committee on Three Dimensional Finite Element Stress Evaluation (C-TDF) in Japan. Thermal stress ratchet criteria in plastic FEA are now under consideration. Two criteria are proposed: evaluating variations in plastic strain increments and evaluating variations in the width of elastic core. To verify the validity of these criteria, calculations were performed for several typical models in C-TDF [2]. This paper shows the results of a simple cylinder model. Cyclic plastic analyses were performed applying sustained internal pressure and alternating linear temperature distribution through the wall. Analyses were performed with various load ranges to evaluate the precise ratchet limit and its behavior across the limit. Both pressure and thermal stress were given parameters. In the analyses, Elastic-Perfectly-Plastic (EPP) material was used and also strain hardening material for comparison. The ratchet limit in the Code [3] is based on Miller’s theoretical analysis [4] for a cylinder assuming a uni-axial stress state, whereas real vessels are in multi-axial stress state. By our calculations, we also examined the ratchet limit in real vessels. The results show that for the cylinder in a multi-axial stress state, the ratchet limit rises 1.2 times the ratchet limit by the Code. The evaluation results show that variations in equivalent plastic strain increments can be used for ratchet criterion and ratcheting can be assessed by confirming the presence of elastic core in the second cycle.Copyright


ASME 2012 Pressure Vessels and Piping Conference | 2012

Underwater Remote Microscopic Observation Technique for 3D Curved Surface of LWR Structures

Satoru Aoike; Koichi Kurosawa; Shinya Ohmori; Masaaki Tanaka

To survey core internals simply, new microscopic observation techniques were developed. These techniques were involved the use of “Gel electrode” and “underwater microscope”. A Gel electrode can etch the surface of core internals without a watertight reservoir that makes an etching environment. The underwater microscope can be used to observe surface figures of core internals directly. These techniques were applied to the cracks detected at the shroud support of Tokai II Power Station for investigation of the cause of crack initiation. It became clear that initiation points of the detected cracks were in a nickel-base weld metal.© 2012 ASME


ASME 2002 Pressure Vessels and Piping Conference | 2002

Effects of Local Peak Stress Distribution on the Ratchet Limit

Nobuyoshi Yanagida; Masaaki Tanaka; Norimichi Yamashita; Yukinori Yamamoto

Alternative stress evaluation criteria suitable for Finite Element Analysis (FEA) proposed by Okamoto et al. [1],[2] have been studied by the Committee on Three Dimensional Finite Element Stress Evaluation (C-TDF) in Japan. Thermal stress ratchet criteria in plastic FEA are now under consideration. Two criteria are proposed: (1) Evaluating variations in plastic strain increments, and (2) Evaluating the width of the area in which Mises equivalent stress exceeds 3Sm . To verify of these criteria, we selected notched cylindrical vessel models as prime elements. To evaluate the effect of the local peak stress distribution on these criteria, cylindrical vessels with a semicircular notch on the outer surface were selected for this analysis. We used two notch configurations for our analysis, and the stress concentration factor for the notches was set to 1.5 and 2.0. We conducted elastic-plastic analysis to evaluate the ratchet limit. Sustained pressure and alternating enforced longitudinal displacements which causes secondary stress were used as parameters for the elastic-plastic analysis. We found that when no ratchet was observed, the equivalent plastic strain increments decreased and the area in which Mises equivalent stress exceeds 3Sm are below the certain range.Copyright


Archive | 1999

Humidity control apparatus

Taisei Hosoda; Hideo Uzuhashi; Nobuyuki Kobayashi; Masaaki Tanaka


Archive | 1973

FIVE-WAY REVERSING VALVE

Taisei Hosoda; Hideo Uzuhashi; Nobuyuki Kobayashi; Masaaki Tanaka


Archive | 2009

Underwater remote surface inspection method and apparatus for reactor constituting member

Satoru Aoike; Masaaki Tanaka; Koichi Kurosawa


Archive | 2013

Method of Repairing Shroud Support and Repair Apparatus Thereof

Shinya Ohmori; Koichi Kurosawa; Masaaki Tanaka; Takanori Satoh


Atomic Energy Society of Japan | 2017

Issues and Challenges for Simulation Credibility Assessment

Masaaki Tanaka


Atomic Energy Society of Japan | 2016

Development of Multiscale Numerical Simulation Method for Thermal Transient Phenomena of Sodium-cooled Fast Reactor

Masaaki Tanaka


Atomic Energy Society of Japan | 2014

Practical procedure of V&V for numerical estimation of high cycle thermal fatigue in FBR

Masaaki Tanaka

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