کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
297545 511761 2011 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Steam leak detection in advance reactors via acoustics method
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Steam leak detection in advance reactors via acoustics method
چکیده انگلیسی

Prediction of LOCA (loss of coolant activity) plays very important role in safety of nuclear reactor. Coolant is responsible for heat transfer from fuel bundles. Loss of coolant is an accidental situation which requires immediate shut down of reactor. Fall in system pressure during LOCA is the trip parameter used for initiating automatic reactor shut down. However, in primary heat transport system operating in two phase regimes, detection of small break LOCA is not simple. Due to very slow leak rates, time for the fall of pressure is significantly slow. From reactor safety point of view, it is extremely important to find reliable and effective alternative for detecting slow pressure drop in case of small break LOCA. One such technique is the acoustic signal caused by LOCA in small breaks. In boiling water reactors whose primary heat transport is to be driven by natural circulation, small break LOCA detection is important. For prompt action on post small break LOCA, steam leak detection system is developed to detect any leak inside the reactor vault. The detection technique is reliable and plays a very important role in ensuring safety of the reactor. Methodology developed for steam leak detection is discussed in present paper. The methods to locate the leak is also developed and discussed in present paper which is based on analysis of the signal.


► Steam leak detection system is developed to detect any leak inside the reactor vault.
► The technique uses leak noise frequency spectrum for leak detection.
► Testing of system and method to locate the leak is also developed and discussed in present paper.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 241, Issue 7, July 2011, Pages 2448–2454
نویسندگان
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