Zobrazeno 1 - 10
of 75
pro vyhledávání: '"Neutron flux density"'
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 1, Pp 140-146 (2023)
The ex-core nuclear instrument equipment consists of the source range detector, the start-up and work range detector and the refueling monitoring range detector in Tianwan nuclear power plant (NPP). The neutron flux density of the reactor is monitore
Externí odkaz:
https://doaj.org/article/cd9d2103be664ffc93b4b3c62794324b
Akademický článek
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Publikováno v:
Âderna Fìzika ta Energetika, Vol 22, Iss 3, Pp 243-248 (2021)
A program for calculating the spectra and densities of neutron fluxes in the experimental channels of the research reactor WWR-M was developed. To do this, the reactor core was modeled. Irradiation of neutron activation detectors was performed. The o
Externí odkaz:
https://doaj.org/article/db37f5fb05cd48beace1157b21e85488
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 1, Pp 121-126 (2022)
The relative neutron flux density distribution is one of the essential physical parameters of the reactor. Measuring the relative neutron flux density distribution of the annular fuel zero-power reactor core has guiding significance for understanding
Externí odkaz:
https://doaj.org/article/d4c1cf5ae6a041b0ad38a6c84fc083b5
Akademický článek
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Publikováno v:
East European Journal of Physics, Vol 4, Iss 4, Pp 42-52 (2017)
The energy and pulse height spectrums after passage of neutron radiation through samples of materialsmost often used to protect against neutron radiation (paraffin, paraffin with boric acid, paraffin with boric acid and lead, polyethylene, polyethyle
Externí odkaz:
https://doaj.org/article/7e141dddd52046b98629934672257ac4
Publikováno v:
Âderna Fìzika ta Energetika, Vol 18, Iss 2, Pp 125-135 (2017)
Measurements of the transmission of neutrons through two samples of 235U and Cd, which are simultaneously on neutron beam, with different sequence of their location for different exposure times of the samples on the beam, are performed. Previously ob
Externí odkaz:
https://doaj.org/article/f9d41adbf3034a27a4722e355865f9d9
Autor:
Ruslan A. Vnukov, Masum Rana Pramanik, Irina A. Zhavoronkova, Yaroslav A. Kotov, Valery V. Kolesov
Publikováno v:
Nuclear Energy and Technology 7(3): 215-221
Nuclear Energy and Technology, Vol 7, Iss 3, Pp 215-221 (2021)
Nuclear Energy and Technology, Vol 7, Iss 3, Pp 215-221 (2021)
Optimizing the use of fuel in a power reactor is a task of current concern. However, little attention has been given to investigating the dependences among the enrichment used, the content of gadolinium oxide in fuel elements, and the life time in co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::de334c12624c496dc0d80bc6a3d1003d
https://doi.org/10.3897/nucet.7.73490
https://doi.org/10.3897/nucet.7.73490
Publikováno v:
Науковий журнал «Енергетика: економіка, технології, екологія»; № 2 (2022)
POWER ENGINEERING: economics, technique, ecology; No. 2 (2022)
POWER ENGINEERING: economics, technique, ecology; No. 2 (2022)
The article uses the adiabatic modelling method for slow transient processes in nuclear reactors. The essence of this method is that the spatial component of the neutron flux density is determined by the solution of static equations of neutron transp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=scientific_p::2304507baf6b20606806595be3a4f86e
http://energy.kpi.ua/article/view/261376
http://energy.kpi.ua/article/view/261376
Autor:
Zhou, Xuan
In dieser Forschungsarbeit wurde die ortsabhängige Neutronenflussdichteverteilung des Ausbildungskernreaktors AKR-2 untersucht. Ziel der Arbeit war es, die radiale und tangentiale Verteilung der Neutronenflussdichte experimentell zu messen und diese
Externí odkaz:
https://tud.qucosa.de/id/qucosa%3A94086
https://tud.qucosa.de/api/qucosa%3A94086/attachment/ATT-0/
https://tud.qucosa.de/api/qucosa%3A94086/attachment/ATT-0/
