Delayed Neutron Measurement in High Frequency Mode and Its Application to the Determination of Fissile Content in Spent Fuel Assembly

被引：0
|
作者：
Lee, Tae-Hoon [1 ]
Shin, Hee-Sung [1 ]
Kim, Ho-Dong [1 ]
机构：
[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea
来源：
2011 IEEE NUCLEAR SCIENCE SYMPOSIUM AND MEDICAL IMAGING CONFERENCE (NSS/MIC) | 2011年
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中图分类号：
TM [电工技术]; TN [电子技术、通信技术];
学科分类号：
0808 ; 0809 ;
摘要：
The delayed neutron measurement has been used for the fresh fuel inspection and U-235 enrichment measurement of uranium materials for many years. The origin of delayed neutron is the beta decay of fission fragments and the population of fission fragments of right after a fission event decreases as time goes by. In the process of optimization of delayed neutron measurement system using a DT neutron generator to determine the fissile content of spent fuel assembly, we could find out that the utilization of delayed neutron can be maximized by performing the data acquisition of delayed neutron in an earlier time after the fission event. Monte Carlo code simulation results show the delayed neutron count rate obtained in a high frequency mode (100 Hz) is 3.25 times bigger than that acquired in a low frequency mode (0.5 Hz). The influence of delayed neutrons by U-238 fission on delayed neutron counts is not negligible. Thus the delayed neutron count rate for 64 cases of spent fuel assembly is corrected by considering the U-238 influence. To obtain sufficiently large ratios of signal to background for many cases of spent fuel assembly, 10(10) similar to 10(11) n/s strength of DT neutron generator is needed.
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页码：2245 / 2251
页数：7
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