Automated analysis for large amount gaseous fission product gamma-scanning spectra from nuclear power plant and its data mining

2010 ◽  
Vol 284 (3) ◽  
pp. 647-651 ◽  
Author(s):  
Weihua Zhang ◽  
Jarmo Ala-Heikkila ◽  
Kurt Ungar ◽  
Ian Hoffman ◽  
Ryan Lawrie
Author(s):  
Yin Yuhao ◽  
Huang Yichao ◽  
Zhao Feng

The Westinghouse Owners Group Core Damage Assessment Guidance (CDAG), which has been authorized by the NRC staffs, is now used by licensee emergency response organization staff for estimating the extent of core damage that may have occurred during an accident at a Westinghouse nuclear power plant. On the other hand, EPR is a 3rd generation nuclear power plant, which applies the advanced European nuclear power technology. This paper introduced Core Damage Assessment Guidance methodology in detail. The CDAG methodology is then attempted to apply to the EPR nuclear power plant. Detailed calculations have been performed for the setpoints of containment radiation monitors (CRM) and core exit thermocouples (CETs) with EPR design characteristics, which are the two main methods for estimation core damage amount. This paper also focuses the discussion on the reasons of difference of core damage estimating results between CRM method and CETs method; based on the discussion, several advices are provided when the two methods show a reasonable discrepancy in conclusions. Several conclusions can be made from the discussions in this article that 1)the Westinghouse Owners Group CDAG methodology proved to be reasonable when applied to EPR power plant for core damage assessment under severe accident; 2) the CDAG methodology which reflect the latest understanding of fission product behavior, is very simple and timely for core damage assessment based on NPP (nuclear power plant) real-time parameters; 3) conservative calculation results of setpoints on CRM and CETs based on EPR design show a reasonable trend and range; 4) it is concluded that several factors such as the releasing way, RCS fission product retention, fuel burnups might have great impact on the estimating results, when the results from two main indications (CRM and CETs) show an unexpected response.


2014 ◽  
Vol 23 (3) ◽  
pp. 186-190
Author(s):  
Dong Soo Song ◽  
Sang Jun Ha ◽  
Je Joong Seong ◽  
Hwang Yong Jeon ◽  
Seong Cheol Huh

Author(s):  
Jin Beak Park ◽  
Kun Jai Lee ◽  
Duck Won Kang ◽  
Dae Hwan Kim

Abstract In 1996, the fully automated radionuclide assay system, which is used for the non-destructive analysis and for the evaluation of radioactive waste drums, was installed at Kori nuclear power plant site and started to operate. The system is composed of gamma scanning hardware facility, equipment for separation and detection of non-gamma radionuclide, scaling factor prediction program, and control facility for radionuclide assay system. In this study, the operational status and results of radionuclide assay system are investigated from the experience of several years of operation. The results of the radionuclide assay system are compared with the results of dose to curie conversion program (DOSE).


2015 ◽  
Vol 103 (10) ◽  
Author(s):  
Teemu Kärkelä ◽  
Ari Auvinen ◽  
Tommi Kekki ◽  
Petri Kotiluoto ◽  
Jussi Lyyränen ◽  
...  

AbstractIodine is one of the most radiotoxic fission product released from fuel during a severe nuclear power plant accident. Within the containment building, iodine compounds can react e.g. on the painted surfaces and form gaseous organic iodides.In this study, it was found out that gaseous methyl iodide (CH


The Power Plants are engineered and instrumented to ensure safety in all modes of operation. Hence they should be continuously monitored and maintained with necessary Instrumentation to identify performance degradation and the root causes to avoid calling for frequent maintenance. The degraded performance of Instrumentation & Control systems may also lead to plant outages. Different studies have suggested that a well maintained instrumentation with errors and response times within the permissible limits may increase the availability minimizing outages. The I&C systems are designed for monitoring, control and safety actions in case of an event in a power plant. The sensors used are single, redundant, triplicated or diverse based on the type of application. Where safety is of prime concern, triplicated and 2/3 voting logic is employed for initiating safety actions. Diverse instruments are provided for protecting the plant from any single abnormal event. Redundant sensors are used to improve plant availability. Wherever 2/3 logics are used, the sensors shall uniformly behave and the drifts across the sensor may lead to crossing the threshold, initiating a protective action. Instead of waiting for the regular preventive maintenance schedule for recalibrating the sensors, the drift in the sensors are analyzed by developing a combined overall online monitoring parameter which will give an early warning to the operator the need for recalibration of the redundant sensors. This paper deals with development of one such parameter through data mining techniques for a representative process in a nuclear power plant.


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