ZHENG Chun, WANG Qiang, LI Meng, DAI Shao-feng. Measurement of Total Fission Number by Delayed Neutron Method for Burst Reactor[J]. Atomic Energy Science and Technology, 2007, 41(6): 699-701. DOI: 10.7538/yzk.2007.41.06.0699
Citation: ZHENG Chun, WANG Qiang, LI Meng, DAI Shao-feng. Measurement of Total Fission Number by Delayed Neutron Method for Burst Reactor[J]. Atomic Energy Science and Technology, 2007, 41(6): 699-701. DOI: 10.7538/yzk.2007.41.06.0699

Measurement of Total Fission Number by Delayed Neutron Method for Burst Reactor

  • ased on the comparison of the delayed neutron counter rate of known fission rate with the delayed neutron counter rate of a burst, a method to determine burst total fission number of burst reactor was built. The relative standard uncertainty of total fission number is 4% using BF3 long counters as detector. The measured 30 burst total fission numbers are according with that from other methods.
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