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Standard Practice for Application of CaF2(Mn) Thermoluminescence Dosimeters in Mixed Neutron-Photon Environments
NORMA vydaná dňa 1.1.2023
Označenie normy: ASTM E2450-23
Dátum vydania normy: 1.1.2023
Kód tovaru: NS-1099218
Počet strán: 6
Približná hmotnosť: 18 g (0.04 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM
Keywords:
dosimetry, gamma, LET, mixed-field, neutron, TLD,, ICS Number Code 17.240 (Radiation measurements)
Significance and Use | ||||||||||||||||
4.1?Electronic devices are typically tested for device response to gamma radiation in pure gamma-ray fields. Testing electronic device response against neutrons is more complex since there is invariably a gamma-ray component in addition to the neutron field. The gamma-ray response of the electronic device is typically subtracted from the overall response to find the device response to neutrons. This approach to the testing requires a determination of the gamma-ray exposure in the mixed field. To enhance the neutron effects, the radiation field is sometimes selected to have as large a neutron component as possible. 4.2?CaF2(Mn) TLDs are often used to monitor the gamma-ray dose in mixed neutron/gamma radiation fields. Since the dosimeters are exposed along with the device under test to the mixed field, their response must be corrected for neutrons. In a field rich in neutrons, the uncertainty in the interpretation of the TLD response grows. In fields with relatively few neutrons, the total TLD response may be used to make a correction for gamma response of the device under test. Under this condition, the relative uncertainty in the TLD neutron response is not likely to drive the overall uncertainty in the correction to the electronic device response. 4.3?This practice gives a means of estimating the response of CaF4.4?Should the user find the resulting uncertainties too large for his purposes, the neutron response of the CaF4.5?Neutron effects on electronics under test are usually reported in terms of 1-MeV(Si) equivalent fluence (Practice E722). Neutron effects of TLDs, as discussed here, are reported in units of absorbed dose, since they are corrections to the gamma-ray dose. |
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1. Scope | ||||||||||||||||
1.1?This practice describes a procedure for correcting a CaF1.2?More precise experimental techniques may be applied if the uncertainty derived from this practice is larger than the level that the user can accept. These more precise techniques are not discussed here. The references in Section 8 describe some of these techniques. 1.3?This practice does not discuss effects on the TLD reading from neutron interactions with the material surrounding the TLD and used to ensure a charged particle equilibrium. These effects will depend on the isotopic composition of the surrounding material and its thickness, and on the incident neutron spectrum (1).2 1.4?The values stated in SI units are to be regarded as standard. 1.5?This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. |
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2. Referenced Documents | ||||||||||||||||
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