Method for defining the concentration of fissile materials in radioactive waste

In the work the development materials of an industrial technique definition of fission materials concentration in radioactive waste are resulted. The active analysis lays on the basis of a technique. Researched samples were irradiated with flows of neutrons received on the basis of the electron line...

Повний опис

Збережено в:
Бібліографічні деталі
Дата:2000
Автори: Buki, A.Yu., Kasilov, V.I., Kirichenko, V.V., Kokhnyuk, К.S., Lapin, N.I., Noga, V.I.
Формат: Стаття
Мова:English
Опубліковано: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2000
Назва видання:Вопросы атомной науки и техники
Теми:
Онлайн доступ:http://dspace.nbuv.gov.ua/handle/123456789/82285
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Назва журналу:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Цитувати:Method for defining the concentration of fissile materials in radioactive waste / A.Yu. Buki, V.I. Kasilov, V.V. Kirichenko, К.S. Kokhnyuk, N.I. Lapin, V.I. Noga // Вопросы атомной науки и техники. — 2000. — № 2. — С. 64-65. — Бібліогр.: 5 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine
Опис
Резюме:In the work the development materials of an industrial technique definition of fission materials concentration in radioactive waste are resulted. The active analysis lays on the basis of a technique. Researched samples were irradiated with flows of neutrons received on the basis of the electron linear accelerator. Experiment was carried out on ELE - 300 NSC KIPT using neutron - making target made of Pb (5 cm in diameter and 4 cm in thickness). At an electron beam energy of 20 МeV and an average current of 1 mА such a target can produce a total neutron flux of about 2x10¹⁰s⁻¹. The achieved sensitivity by definition of concentration ²³⁵U is at the level 10⁶ g/g.