Abstract Thermal fatigue crack may initiate at mixing tee where high and low temperature fluids flow in and mix. In order to prevent piping failure caused by thermal fatigue, an evaluation procedure of fluid temperature fluctuation at mixing tee using numerical simulation has been de veloped. This paper compared results of three computational grids of different resolution and discussed the effect of the grids resolution on predictions. The same simulation conditions were set same as WATLON experiments perf...
英字タイトル:
Numerical Simulation of Temperature Fluctuation Downstream from a T-Junction-Evaluation of Computational Grid Influence Using LES Dynamic Model

１．はじめに本文 １ 総則２ 測定３ 評価及び対策立案４ 記録５ 力量要件附属書 １ 赤外線サーモグラフィーによる測定、評価の例２ 評価時の留意点(測定値補正の例)３ 赤外線の放射率について日本における設備診断は、一般産業界では広く活用されてきてはいるものの、原子力発電所での適用実績が少なく、その方法や施策等が必ずしも確立されていない。日本電気協会では、原子力発電所で設備診断を導入する際の参考として各種診断技術を適用する際の指針を検討してきており、既に回転機械振動診断技術(JEAG4221)、潤滑油診......

In this study, the corrosion rate on the pipe wall downstream from an orifice was measured in order to validate the evaluation code for flow-accelerated corrosion (FAC). Three orifices with aperture ratios . = 0.62, 0.50, 0.41 was used in a test section with 50mm inner pipe diameter. The flow velocity was changed during the test to investigate the effect of mean cross-sectional flow velocity on the FAC rate. The water conditions were 150 degree centigrade, about 0.1ppb of dissolved oxygen concentration...
英字タイトル:
FAC Rate Measurement downstream from an Orifice

Condition Based Maintenance (CBM) includes Condition Monitoring (CM) of equipments and performing reasonable frequency on the maintenance work by CM. To improve safety and reliability of equipment s and facilities, CBM has been applied to many industries in Japan and foreign countries from 1970's. On the other hand, in Japanese nuclear power plants, we used to carry out the Time Based Mainte nance (TBM) which is performed constant period of maintenance for the facilities. By the situation of these days, To...
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Application of Condition Monitoring in JAPC

Nuclear piping has various kinds of thermal fatigue failure modes. Main causes of thermal loads are structural responses to fluid temperature changes during plant operation. These phenomena have complex mechanisms and so many patterns, that their problems still occur even though well-known issues. To prevent thermal fatigue due to above thermal loads, the JSME guideline is adopted. Both thermal load and fatigue failure mechanism have been investigated and summarized into the knowledgebase. Based on abo...
英字タイトル:
Development of thermal fatigue evaluation methods of piping systems