Design of Neutron Flux Monitoring System for Sodium Cooled Fast Reactors

被引:0
|
作者
Nagaraj, C. P. [1 ]
Sivaramakrishna, M. [1 ]
Madhusoodanan, K. [2 ]
Chellapandi, P. [3 ]
机构
[1] IGCAR, PPG RDG, NIS ICD, Kalpakkam, Tamil Nadu, India
[2] PPG RDG, IGCAR, Kalpakkam, Tamil Nadu, India
[3] RDG, IGCAR, Kalpakkam, Tamil Nadu, India
关键词
neutron flux; PFBR; high temperature fission chamber; pulse mode; Campbell mode;
D O I
暂无
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
Neutron Flux Monitoring System (NFMS) plays an important role in the safety of sodium cooled fast reactors. NFMS measures the reactor power and the reactivity changes in the core. The neutron detectors sense the neutron flux at suitable locations representing the core flux and the signal conditioning electronics processes the signal to get logarithmic power, linear power, period and reactivity parameters. These parameters aid in control of reactor power and initiate safety action on crossing the threshold.
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页数:7
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