• Journal of Energy Engineering
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• v.16 no.4
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• pp.155-163
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• 2007

To insure nuclear reactor safety, the reactivity of control rods should be calculated by measuring the criticality of reactor core and it is regularly performed during the annual physics test period. Also, the core criticality should be monitored during the start-up operation to avoid reactivity induced accidents. Many research works on control rod reactivity measurement and subcriticality measurement have been accomplished throughout the world for decades and recently a new method named "Modified Neutron Source Multiplication Method (MNSM)" was proposed in Japan which is known to be improved overcoming limitations of traditional Neutron Source Multiplication Method (NSM). In this study, MNSM was tested in calculation of subcriticalities and in evaluation of application validity using the educational reactor in Kyung Hee University, AGN-201. For this study, a revised nuclear data library and a neutron transport code system TRANSX - PARTISN were established. Correction factors for various control rod positions were produced using the k-effective values and the corresponding flux distributions and adjoint flux distributions. Experimental values of the core criticality were obtained using the neutron count rates of the BF3 proportional counters. The results showed that the expected reactivity worth of control rods by MNSM agreed well with the theoretical values and the correction factors contributed much for this purpose.

• Journal of the Korean Institute of Telematics and Electronics
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• v.10 no.4
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• pp.60-73
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• 1973

The reactor noise analysis was performed by the cross correlation method using two detectors to determine the dynamic stability and the system parameter of TRIGA Mark-II reactor under critical and subcritical conditions. The a values turned out to be 46.67 and 70.04 respectively at zero power and full power under critical condition, while 79.47 and 97.59 respectively at the safety rod dropping and the regulating rod dropping under subcritical condition. Prompt neutron life time of TRIGA Mark-II reactor measured 107 and 160 $\mu$sec, and shut down margin was -10.03$\times$10-4 at the safety rod dropping and -29-43$\times$10-4 at the regulating rod dropping CDC 3100/MSOS digital computer, HITACHI 505 Analog computer, and preamplifier, bandpass filter, FM modulator or demodulator designed for this specific purpose, were employed for the present investigation.