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AKYÜREK, TAYFUN

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2019 - 201912020 - 20211
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Subject: FISSION ×

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Now showing 1 - 2 of 2
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    PublicationOpen Access
    Delayed fast neutron as an indicator of burn-up for nuclear fuel elements
    (KOREAN NUCLEAR SOC, 2021-10) AKYÜREK, TAYFUN; Akyurek, T.; Shoaib, S. B.; Usman, S.
    Feasibility study of burn-up analysis and monitoring using delayed fast neutrons was investigated at Missouri University of Science and Technology Reactor (MSTR). Burnt and fresh fuel elements were used to collect delayed fast neutron data for different power levels. Total reactivity varied depending on the burn-up rate of fuel elements for each core configuration. The regulating rod worth was 2.07E-04 Dk/k/in and 1.95E-04 Dk/k/in for T121 and T122 core configurations at 11 inch, respectively. Delayed fast neutron spectrum of F1 (burnt) and F16 (fresh) fuel elements were analyzed further, and a strong correlation was observed between delayed fast neutron emission and burn-up. According to the analyzed peaks in burnt and fresh fuels, reactor power dependency was observed and it was determined that delayed neutron provided more reliable results at reactor powers of 50 kW and above. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
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    PublicationOpen Access
    Determination of plutonium and uranium content and burnup using six group delayed neutrons
    (KOREAN NUCLEAR SOC, 2019-07) AKYÜREK, TAYFUN; Akyurek, T.; Usman, S.
    In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium free fuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. Pu-239 conversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.