SU394741A1 - METHOD FOR SELECTING RADIATION-STRENGTH - Google Patents

METHOD FOR SELECTING RADIATION-STRENGTH

Info

Publication number
SU394741A1
SU394741A1 SU1688079A SU1688079A SU394741A1 SU 394741 A1 SU394741 A1 SU 394741A1 SU 1688079 A SU1688079 A SU 1688079A SU 1688079 A SU1688079 A SU 1688079A SU 394741 A1 SU394741 A1 SU 394741A1
Authority
SU
USSR - Soviet Union
Prior art keywords
radiation
strength
detectors
selecting radiation
ultraviolet
Prior art date
Application number
SU1688079A
Other languages
Russian (ru)
Inventor
Н. Ю. Гуревич А. Л. Лифнц И. С. Буднлов Ю. А. Цирлин
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed filed Critical
Priority to SU1688079A priority Critical patent/SU394741A1/en
Application granted granted Critical
Publication of SU394741A1 publication Critical patent/SU394741A1/en

Links

Landscapes

  • Measurement Of Radiation (AREA)

Description

1one

Изобретение относитс  к области дозиметрии и радиометрии радиоактивных излучсиии.The invention relates to the field of dosimetry and radiometry of radioactive radiation.

Распространенным критерием радиационной прочности кристаллов йодистого натри , активированного таллием,  вл етс  достаточно мала  фонова  скорость счета, измер ема  через 10 мин после воздействи  на кристалл гамма-излучени  мощностью дозы в 60 рчас в течение 1 -1,5 час При низких порогах дискриминацни ,A common criterion for the radiation strength of sodium iodide crystals activated by thallium is the relatively low background count rate, measured 10 minutes after gamma radiation is applied to a crystal with a dose rate of 60 h for 1 -1.5 hours. At low thresholds of discrimination,

Обычно на раднацлюиную прочность провер ют уже готовые детекторы определенных размеров в спепнальной упаковке. Образцы, не выдержавшие испытани  ло этому параметру , не могут быть использованы дл  друтих щелей н идут в отходы. Это приводит к непронзводитсльным затратам рабочего времени и материалов, требуемых дл  изготовлеии  детекторов п измерени  их радиационной лрочиости.Usually, ready-made detectors of certain dimensions in speckle packaging are checked for radar blue strength. Samples that did not withstand this parameter cannot be used for other gaps or waste. This leads to non-intrusive expenditures of working time and materials required for the manufacture of detectors and the measurement of their radiation sensitivity.

Дл  снижени  затрат на нзготовлеиие н испытанпе детекторов п сокращени  продолжительности процесса ло предлагаемому способу облучают монокристаллы ультрафиолетовым излу-чением до его контейнеризации. Облучение Т роиз1юд т в течеиие I -10 сек.In order to reduce the cost of preparation and testing of detectors and reduce the duration of the process, the proposed method is exposed to single crystals with ultraviolet radiation prior to its containerization. The irradiation of T roizyyudt during I-10 sec.

Через 10 мин лосле облучени  измер ют ток послесвечени .After 10 minutes, the afterglow current is measured by the irradiation loop.

Между током послесвечени  заготовок йодистого иатри , активированного таллием, облучс1шых ультрафиолетовым светом, и фоновой скоростью счета облученных гамма-радиацией детекторов, изготовлеиных на их осиове, существует однозначна  зависимость.There is an unambiguous dependence between the current of the afterglow of iodine and sodium preforms activated with thallium irradiated with ultraviolet light and the background count rate of gamma-irradiated detectors fabricated on their axis.

Это позвол ет при иаличин градунровочной кривой по току послесвечени  крпсталла, облученного ультрафиолетом, судить о его пригодиостн дл  нзготовленн  сцннтнлл цнонного детектора. Мощность н доза ультрафиолетового облучеии  выбираютс  такими, чтобы не вызвать необратимых нзменений в кристалле.This makes it possible to judge its usefulness for the preparation of a laser detector with a UV detector when it is equal to the current curve of the afterglow of an ultraviolet crystal. The power and dose of ultraviolet irradiation are chosen so as not to cause irreversible changes in the crystal.

Предмет изобретени Subject invention

Способ отбора радиационнопрочных монокристаллов подпетого натри , активированного тал,, путем облучени  возбуждающим излучением с иоследующим измерением послссвеченн , отличаюи ийс  тем, что, с целью снижени  затрат на изготовление и испытание детекторов и -сокращени  продолжлтельностн процесса, монокрпсталлы облучают ультрафиолетовым излучеиием до его Контейнеризации .The method of selection of radiation-resistant monocrystals of the injected sodium activated tal by irradiation with excitation radiation and subsequent measurement is recent, differing in that, in order to reduce the cost of fabrication and testing of detectors and shortening the process, monocrystals irradiate with ultraviolet radiation and ultraviolet radiation and radiation will decrease with the duration of the process.

SU1688079A 1971-08-09 1971-08-09 METHOD FOR SELECTING RADIATION-STRENGTH SU394741A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
SU1688079A SU394741A1 (en) 1971-08-09 1971-08-09 METHOD FOR SELECTING RADIATION-STRENGTH

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SU1688079A SU394741A1 (en) 1971-08-09 1971-08-09 METHOD FOR SELECTING RADIATION-STRENGTH

Publications (1)

Publication Number Publication Date
SU394741A1 true SU394741A1 (en) 1973-08-22

Family

ID=20485068

Family Applications (1)

Application Number Title Priority Date Filing Date
SU1688079A SU394741A1 (en) 1971-08-09 1971-08-09 METHOD FOR SELECTING RADIATION-STRENGTH

Country Status (1)

Country Link
SU (1) SU394741A1 (en)

Similar Documents

Publication Publication Date Title
SU394741A1 (en) METHOD FOR SELECTING RADIATION-STRENGTH
Piesch et al. Activation and damage effects in TLD 600 after neutron irradiation
US2935613A (en) Continuously readable dosimeters
Parsons et al. Photodisintegration of the Heavy Elements
KR950001738B1 (en) Detection of nuclear radiation
RU2025800C1 (en) Method for determination of content of boron-10 in heat carrier of the first circuit of nuclear reactor
Katayama The Transient Absorption of Irradiated α-Methylstyrene
Puite Thermoluminescent sensitivity of CaF2: Mn in a mixed neutron-gamma field
Miller et al. Precision high-speed neutron activation analysis via very short-lived activities
IE35942B1 (en) Improved radiological well logging methods and apparatus
US3899679A (en) Manganese activated phosphate glass for dosimetry
RU2068571C1 (en) Method of distant detection of nuclear charges
Jain Phototransfer, sensitization and re-estimation of dose in lithium fluoride TLD
GB1248030A (en) Apparatus for measuring the content of fissile substance of fuel elements or the burn-up of fuel elements, of a nuclear reactor
Schulman Solid state dosimeters for radiation measurement
GB1154825A (en) A method of, and a device for, Determining the Isotope Content of a Uranium Component
SU448771A1 (en) Activation Analysis Method
SU439740A1 (en) Method for determining concentration of fissile material
US3453430A (en) Controlled defect coloration dosimeter
Raju et al. Fast neutron spectrum of Ra Be source
Hsu et al. Measurement of thermal neutrons and gamma-rays in a mixed radiation field based on capture gamma or self irradiation of thermoluminescent dosimeters
Draper et al. Soft gamma rays from Eu152 and Eu154 following resonance neutron capture
SU468553A1 (en) Neutron sensor
RU93027874A (en) METHOD OF DOSYMETRY OF GAMMA- AND NEUTRON RADIATION AND DEVICE FOR ITS IMPLEMENTATION
SU274859A1 (en) Method for quntitative neutron analysis of elemental composition of substance