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RU2218584C2 - Method measuring neutron yield - Google Patents

Method measuring neutron yield Download PDF

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Publication number
RU2218584C2
RU2218584C2 RU2001127277A RU2001127277A RU2218584C2 RU 2218584 C2 RU2218584 C2 RU 2218584C2 RU 2001127277 A RU2001127277 A RU 2001127277A RU 2001127277 A RU2001127277 A RU 2001127277A RU 2218584 C2 RU2218584 C2 RU 2218584C2
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RU
Russia
Prior art keywords
time interval
interval
relation
pulses
neutron
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RU2001127277A
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Russian (ru)
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RU2001127277A (en
Inventor
О.С. Морозов
В.М. Новиков
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Федеральное государственное унитарное предприятие "Всероссийский научно-исследовательский институт автоматики им. Н.Л.Духова"
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Priority to RU2001127277A priority Critical patent/RU2218584C2/en
Publication of RU2001127277A publication Critical patent/RU2001127277A/en
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Abstract

FIELD: recording and controlling neutron yield of pulse source of type of neutron generator. SUBSTANCE: method measuring neutron yield of pulse source is based on measurement of two activation detectors with different half-life periods in the course of two specified time intervals after input of neutron pulse by single recording channel. Delay between two specified time intervals is chosen on condition of obtainment of extremum of derivative of relation C2/C1 depending on delay of specified time intervals relative to input of neutron pulse. Duration of second time interval is chosen from relation t2 = t1λ12, Activity per each time interval is measured in two corresponding subintervals. Relation C11/C12 is utilized to control value of first time interval and relation C23/C24 is used to control second time interval. Duration of subintervals of second time interval is chosen in proportion to duration of first subintervals with proportionality factor λ12, where C1 is counting of pulses of induced activity in first time interval t1, C2 is counting of pulses of induced activity in second time interval t2, λ1- is decay constant of first radio nuclide, λ2 is decay constant of second radio nuclide, C11 is counting of pulses in first subinterval, C12- is counting of pulses in second subinterval, C23 is counting of pulses in third subinterval, C24 is counting of pulses in fourth subinterval. EFFECT: enhanced authenticity of measurement of neutron yield, simplified measurement process. 4 cl, 3 dwg

Description

Текст описания в факсимильном виде (см. графическую часть). Description text in facsimile form (see graphic part).

Claims (5)

1. Способ измерения выхода нейтронов импульсного источника на основе двух активационных детекторов с различным периодом полураспада, заключающийся в измерении фона детекторов до прихода нейтронного импульса и наведенной активности детектора в течение двух заданных промежутков времени после прихода нейтронного импульса, отличающийся тем, что наведенную активность измеряют одним регистрационным каналом, а задержку между двумя заданными промежутками времени выбирают из условия получения экстремума производной отношения С21 в зависимости от задержки заданных промежутков времени относительно прихода нейтронного импульса, где С1 - счет импульсов наведенной активности за первый промежуток времени t1, C2 - счет импульсов наведенной активности за второй промежуток времени t2, длительность которого выбирают из соотношения t2 = t1λ1 / λ2, где λ1 - постоянная распада первого радионуклида, λ2 - постоянная распада второго радионуклида, после чего проверяют соответствие измеренного отношения С21 расчетному значению из уравнения радиоактивного распада смеси радионуклидов активационного детектора, при этом измерение активности за каждый промежуток времени проводят в двух соответствующих подинтервалах, причем по отношению С1112 контролируют значение первого промежутка времени, а по отношению С2324 контролируют второй промежуток времени, где С11 - счет импульсов за первый подинтервал, С12 - счет импульсов за второй подинтервал, где С23 - счет импульсов за третий подинтервал, С24 - счет импульсов за четвертый подинтервал, а длительности подинтервалов второго промежутка времени выбирают пропорционально длительности первых подинтервалов с коэффициентом пропорциональности λ12.1. The method of measuring the neutron yield of a pulsed source based on two activation detectors with different half-lives, which consists in measuring the background of the detectors before the arrival of the neutron pulse and the induced activity of the detector for two predetermined time intervals after the arrival of the neutron pulse, characterized in that the induced activity is measured by one the registration channel, and the delay between two predetermined time intervals is selected from the condition for obtaining the extremum of the derivative of the C 2 / C 1 ratio depending the delay time of predetermined time intervals relative to the arrival of a neutron pulse, where C 1 is the count of induced activity pulses for the first time interval t 1 , C 2 is the count of induced activity pulses for the second time interval t 2 , the duration of which is selected from the relation t 2 = t 1 λ 1 / λ 2 , where λ 1 is the decay constant of the first radionuclide, λ 2 is the decay constant of the second radionuclide, and then check whether the measured ratio C 2 / C 1 matches the calculated value from the equation of the radioactive decay of the mixture of radionuclides a activation detector, while the activity measurement for each time interval is carried out in two corresponding sub-intervals, and the value of the first time interval is controlled in relation to C 11 / C 12 , and the second time interval is controlled in relation to C 23 / C 24 , where C 11 is the pulse count for the first sub-interval, C 12 is the pulse count for the second sub-interval, where C 23 is the pulse count for the third sub-interval, C 24 is the pulse count for the fourth sub-interval, and the durations of the sub-intervals of the second time interval are selected proportionally to the length the first sub-intervals with the proportionality coefficient λ 1 / λ 2 . 2. Способ по п.1, отличающийся тем, что задержку между нейтронным импульсом и первым промежутком контролируют по отношению С21.2. The method according to claim 1, characterized in that the delay between the neutron pulse and the first interval is controlled in relation to C 2 / C 1 . 3. Способ по п.1, отличающийся тем, что длительность первого промежутка времени t1 выбирают из условия t1 = 1,25/λ1.3. The method according to claim 1, characterized in that the duration of the first time interval t 1 is selected from the condition t 1 = 1.25 / λ 1 . 4. Способ по п.1, отличающийся тем, что длительность первого подинтервала t11 выбирают в диапазоне (0,3-0,4)/λ1.4. The method according to claim 1, characterized in that the duration of the first sub-interval t 11 is selected in the range (0.3-0.4) / λ 1 . 5. Способ по п.1, отличающийся тем, что в качестве активационного детектора используют естественную смесь изотопов серебра 107Ag и 109Ag.5. The method according to claim 1, characterized in that as the activation detector using a natural mixture of silver isotopes 107 Ag and 109 Ag.
RU2001127277A 2001-10-09 2001-10-09 Method measuring neutron yield RU2218584C2 (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111722664A (en) * 2020-05-29 2020-09-29 中国石油天然气集团有限公司 Neutron yield control system and method for neutron generator

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB361754A (en) * 1930-01-09 1931-11-26 Separator Ab Improvements in centrifugal separators
US3931523A (en) * 1973-11-07 1976-01-06 Ambardanishvili Tristan Silova Activation neutron detector
SU1259834A1 (en) * 1985-01-28 2000-01-10 В.М. Багаев ACTIVATING NEUTRON DOSE DETECTOR

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB361754A (en) * 1930-01-09 1931-11-26 Separator Ab Improvements in centrifugal separators
US3931523A (en) * 1973-11-07 1976-01-06 Ambardanishvili Tristan Silova Activation neutron detector
SU1259834A1 (en) * 1985-01-28 2000-01-10 В.М. Багаев ACTIVATING NEUTRON DOSE DETECTOR

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111722664A (en) * 2020-05-29 2020-09-29 中国石油天然气集团有限公司 Neutron yield control system and method for neutron generator

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