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Delayed neutron counting of uranium pins using moderated neutrons from portable DD neutron generator in high frequency mode.
Bily, Tomas; Huml, Ondrej; Belko, Branislav.
Afiliación
  • Bily T; Dept. of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, V Holesovickach 2, Prague, 180 00, Czech Republic. Electronic address: tomas.bily@fjfi.cvut.cz.
  • Huml O; Dept. of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, V Holesovickach 2, Prague, 180 00, Czech Republic.
  • Belko B; Dept. of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, V Holesovickach 2, Prague, 180 00, Czech Republic.
Appl Radiat Isot ; 191: 110527, 2023 Jan.
Article en En | MEDLINE | ID: mdl-36327611
Delayed neutron counting is often used to verify the characteristics of nuclear material. Use of portable neutron generators in high frequency pulsing mode enables effective analysis with higher counting efficiency and lower radiation protection demands. The paper deals with delayed neutron counting of uranium pins with P385 portable DD neutron generator in polyethylene-based setup. Counting is performed in high frequency mode of neutron generator. The viability of such measurement in the frequency range from 100 Hz to 250 Hz was demonstrated and optimal pulsing parameters for P385 neutron generator were found. Delayed neutron counting was then performed for two types of uranium rods. Delayed neutrons were counted both inbetween neutron pulses during neutron generation and once the emission of neutrons stopped. The results were further validated by Monte Carlo (MCNP) simulations. For the geometry of studied rods, the MCNP calculation were done to calculate the dependence of the response to delayed neutrons on rod enrichment, to show the viability to use the method for rod enrichment verification. An option of using cadmium inset in irradiation channel to overcome the effect of self-shielding for samples with higher enrichment was proposed, experimentally tested, and evaluated through MCNP calculations.
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Texto completo: 1 Colección: 01-internacional Base de datos: MEDLINE Asunto principal: Protección Radiológica / Uranio Idioma: En Revista: Appl Radiat Isot Asunto de la revista: MEDICINA NUCLEAR / SAUDE AMBIENTAL Año: 2023 Tipo del documento: Article Pais de publicación: Reino Unido

Texto completo: 1 Colección: 01-internacional Base de datos: MEDLINE Asunto principal: Protección Radiológica / Uranio Idioma: En Revista: Appl Radiat Isot Asunto de la revista: MEDICINA NUCLEAR / SAUDE AMBIENTAL Año: 2023 Tipo del documento: Article Pais de publicación: Reino Unido