Characterization of CdSe thin films deposited by chemical bath solutions containing triethanolamine

Effect of deposition temperature on the structural and optical properties of CdSe QDs thin films deposited by CBD method

Accurate characterization of reductions in the fracture toughness of reactor pressure vessel(RPV) steels due to in-service neutron exposure is very important to the safe and reliable operation of nuclear power plants.The prediction model CIAE-2009 for irradiation embrittlement trend of low copper RPV steels was developed,and irradiation embrittlement data were used to verify the prediction model.The predicted fracture toughness trend indicates that the prediction model CIEA-2009 is correct and reliable.

Prediction Model on Irradiation Embitterment of Low Copper Alloy Reactor Pressure Vessel Steels

Multipurpose reactor of G.A. Siwabessy (RSG-GAS) is a research reactor with 30 MWt operated by BATAN since 1987. This reactor has obtained the permission from the regulatory body of BAPETEN to operate with the silicide fuels up to year 2025. In 2003, an ageing management of RSG-GAS was formed to evaluate the ageing process of the structures, systems, and components of the reactor. To support the ageing management, an inspection activity has been conducted to assess to the primary coolant pipe after 29 years operation. The main objective of this inspection was to determine whether a thinning of the primary pipe has occurred. The method used was the non-destructive test method with ultrasonic device to measure the thickness of pipe installed in place. The measurement was conducted two times in one year time span from 2014 to 2015. The results of measurement at three different places of the primary pipe show that the thinning has been occurred although it is very small. There are two forms of thinning that is occuring, which are the non-axisymmetric and axisymmetric. The non-axisymmetric shape thinning tends to occur in the area of the primary pipe upward of the primary pump, while the axisymmetric shape occurs at the pipe downward of the primary pump. In order to provide certainty to the thinning process at the primary pipe of RSG-GAS, re-testing should be performed routinely every 5 years.

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Analysis of the inspection results on the primary cooling pipe of rsg-gas reactor

Reactor pressure vessel (RPV), the only key component that can not be replaced in nuclear power plants (NPPs), is the main barrier against the radioactive leakage The lifetime of NPPs is dependent heavily on the life of RPV, and thus, the aging and life research on a RPV is a key factor in determining the life extension of NPPs The purpose of this paper is to introduce an aging and life management system for an operating RPV which can be used as a reference of the lifetime extension In order to realize the objective, an aging and life management system was developed It is an comprehensive knowledge management system that integrates decentralized information and serves as a valuable data center Based on the storage and management of RPV state information and operation data, this system provides real-time monitoring of important operating parameters, evaluation of irradiation embrittlement, and RPV aging assessment Therefore, it is anticipated that the developed system can be used as an efficient tool for aging and life estimation of RPV

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Guo Jiang

Papers

Aging and Life Management System of Reactor Pressure Vessel