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Method of measuring fast neutron flux using thermoluminescent dosimeter

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专利汇可以提供Method of measuring fast neutron flux using thermoluminescent dosimeter专利检索,专利查询,专利分析的服务。并且Thermoluminescent phosphors which are susceptible to neutron activation are exposed to a mixed field of radiation. Thermoluminescence resulting from prompt gamma irradiation is removed by a short period of annealing at a high temperature. The phosphors are then stored in a shielded chamber maintained at a sufficiently low temperature to allow accumulation of radiation dose produced by radionuclides formed on neutron activation. The thermoluminescence attributable to this self-irradiation dose is read and correlated to neutron flux or dose. Through use of separate phosphor materials having different threshold energies for neutron activation, energy spectra of fast neutron flux is obtained.,下面是Method of measuring fast neutron flux using thermoluminescent dosimeter专利的具体信息内容。

  • 2. The method of claim 1 wherein both said first and second amounts of stored radiation energy are released as thermoluminescence and are photometrically read to determine total radiation flux and fast neutron fluence.
  • 3. The method of claim 1 wherein said step of shielding said phosphors is accomplished by maintaining said phosphors at a cryogenic temperature and both said heating and reading steps are begun at said cryogenic temperature.
  • 4. The method of claim 1 wherein the temperature at which said annealing step is performed is in excess of the temperature range at which said subsequent heating step is performed.
  • 5. The method of claim 1 wherein said phosphor consists of a substantially pure metallic fluoride salt, said salt being maintained at a temperature below 100* K. while said second amount of stored radiation energy is produced.
  • 6. The method of claim 5 wherein said phosphor consists essentially of CaF2.
  • 7. The method according to claim 1 wherein a plurality of said phosphor materials each having a different energy threshold for neutron absorption are exposed, annealed, shielded, heated and photometrically read to determine energy spectrum of said neutron fluence.
  • 8. The method of claim 7 wherein said plurality of phosphor materials comprise 7LiF, Mg2SiO4:Tb, ZnO:Tm and CaSO4:Dy.
  • 9. The method of claim 1 wherein said step of shielding said phosphor is performed at near ambient temperature and said phosphor is selected from the group of phosphor materials comprising 7LiF and CaSO4:Dy.
  • 10. The method of claim 9 wherein said phosphor is CaSO4:Dy and said steps of heating and reading said phosphor are performed after shielding for a period of one day to determine thermal neutron fluence and again after fourteen days to determine fast neutron fluence.
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