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Preliminary Design of Neutron Flux and Spectrum Diagnostics in NT-TBM

Preliminary Design of Neutron Flux and Spectrum Diagnostics in NT-TBM
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摘要 A special neutron diagnostic system is proposed that facilitates the measurement of neutron fluxes and spectra in the neutronics and tritium production-test blanket module (NTTBM) without interrupting the operation of the International Thermal-nuclear Experimental Reactor (ITER), for studying the multiplication rate in the neutron multiplier and breeding ratio of tritium in the breeder. This system includes an encapsulated foil activation system, micro-fission chamber detectors (MFC), and a compact neutron spectrometer using a natural diamond detector (NDD). A helium coolant loop with a reasonable diameter is designed carefully for every measurement channel that ensures that the neutron detectors and preamplifiers would work well under a high temperature scenario and that the filling rates of the neutron multiplier (beryllium pebble) and tritium breeder material (Li4SiO4) would not decrease excessively (the expected value〉80%) due to the dimensions of the helium coolant loop. A special neutron diagnostic system is proposed that facilitates the measurement of neutron fluxes and spectra in the neutronics and tritium production-test blanket module (NTTBM) without interrupting the operation of the International Thermal-nuclear Experimental Reactor (ITER), for studying the multiplication rate in the neutron multiplier and breeding ratio of tritium in the breeder. This system includes an encapsulated foil activation system, micro-fission chamber detectors (MFC), and a compact neutron spectrometer using a natural diamond detector (NDD). A helium coolant loop with a reasonable diameter is designed carefully for every measurement channel that ensures that the neutron detectors and preamplifiers would work well under a high temperature scenario and that the filling rates of the neutron multiplier (beryllium pebble) and tritium breeder material (Li4SiO4) would not decrease excessively (the expected value〉80%) due to the dimensions of the helium coolant loop.
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2007年第2期219-222,共4页 等离子体科学和技术(英文版)
基金 National Natural Science Foundation of China(No.10175021)
关键词 neutronics and tritium production-test blanket module (NT-TBM) fission chamber detector encapsulated foil activation system neutronics and tritium production-test blanket module (NT-TBM), fission chamber detector, encapsulated foil activation system
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参考文献3

  • 1Bekris N, Boccaccini L V, Chen Y, et al. 2001, Design Description Document for the European helium Cooled Pebble Bed (HCPB) Test Blanket Modules.Germany: Forschungs Zentrum Karlsruhe
  • 2Asai K, Iguchi T, Watanabe K et al. 2004, Detail Design of Ex-Vessel Neutron yield Monitor for ITER. 6th meeting of the ITPA Topical Group on Diagnostics,Naka, Japan
  • 3Krasilnikov A V, Kaneko J, Isobe M, et al., 1997, Rev.Sci. Instru., 68:1720

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