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
来源：
2013 3RD INTERNATIONAL CONFERENCE ON ADVANCEMENTS IN NUCLEAR INSTRUMENTATION, MEASUREMENT METHODS AND THEIR APPLICATIONS (ANIMMA) | 2013年
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.
引用
收藏
页数：7
相关论文
共 50 条
  • [1] Design challenges for sodium cooled fast reactors
    Konomura, Mamoru
    Ichimiya, Masakazu
    JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 250 - 269
  • [2] PRIMARY SYSTEM-DESIGN OF SODIUM-COOLED FAST-REACTORS
    CAMPBELL, RH
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1973, 12 (04): : 357 - 365
  • [3] Comparison of lead- and sodium-cooled fast-neutron reactors
    Sidorenko, VA
    ATOMIC ENERGY, 1999, 86 (03) : 170 - 172
  • [4] Comparison of lead-and sodium-cooled fast-neutron reactors
    V. A. Sidorenko
    Atomic Energy, 1999, 86 : 170 - 172
  • [5] Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor
    Coulon, Romain
    Rohee, Emmanuel
    Dumazert, Jonathan
    Garti, Sara
    Filliatre, Philippe
    Jammes, Christian
    ADVANCEMENTS IN NUCLEAR INSTRUMENTATION MEASUREMENT METHODS AND THEIR APPLICATIONS (ANIMMA 2017), 2018, 170
  • [6] RESEARCH AND DESIGN OF THE SODIUM STEAM FILTER SYSTEM IN LARGE LIQUID METAL COOLED FAST REACTORS
    Wang Leijian
    Lu Yuan
    Xiao Changzhi
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5, 2017,
  • [7] RADIOACTIVITY IN PRIMARY SYSTEM OF SODIUM-COOLED FAST-REACTORS
    ULLMANN, H
    KUNSTLER, K
    RICHTER, W
    KERNENERGIE, 1973, 16 (04): : 96 - 105
  • [8] In vessel neutron instrumentation for sodium-cooled fast reactors: Type, lifetime and location
    Filliatre, P.
    Jammes, C.
    Geslot, B.
    Buiron, L.
    ANNALS OF NUCLEAR ENERGY, 2010, 37 (11) : 1435 - 1442
  • [9] Achieving the competitiveness of sodium cooled fast reactors
    Kochetkov, L.A.
    Malenkov, A.V.
    Poplavskij, V.N.
    Saraev, O.M.
    Suknev, K.L.
    Kiryushin, A.I.
    Atomnaya Energiya, 1997, 83 (06): : 401 - 405
  • [10] FAST BREEDER REACTORS COOLED BY SODIUM AND STEAM
    ENGELMANN, P
    KERNTECHNIK ISOTOPENTECHNIK UND CHEMIE, 1967, 9 (3-4): : 111 - +
12345