Microhardness and Young's modulus of high burn-up UO2 fuel
Journal of Nuclear Materials, 2016 AbstractVickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-up ≥60 GWd/tHM are presented. Their ratio HV0.1/E was found constant in the range 60–110 GWd/tHM. From the ratio and the microhardness values vs porosity, the Young's modulus dependence on porosity was derived and extended to the full radial profile ...
Fabiola Cappia +2 more
exaly +2 more sources
High Burn-up Structure in Nuclear Fuel: Impact on Fuel Behavior [PDF]
EPJ Web of Conferences, 2016 Noirot Jean +6 more
doaj +2 more sources
A study into the dependence of the cladding-fuel pellet gap conductance on burn-up and the effects on the reactor core neutronic performance [PDF]
Nuclear Energy and Technology, 2019 This paper presents the results of the research to study the dependence of the VVER-1000 (1200) cores neutronic characteristics on the cladding – fuel pellet gap conductance coefficient in the process of the fuel burn-up.
Sergey B. Vygovsky +2 more
doaj +3 more sources
Burn up effect on optimal placement of fixed in-core detectors for Tehran research reactor using information theory [PDF]
مجله علوم و فنون هستهای, 2020 Monitoring the power distribution of reactor core is one of the most challenging issues in the safe operation of nuclear reactors. The Number and arrangement of detectors in a core monitoring system should be determined in a way that maximum amount of ...
M.S. Terman +2 more
doaj +1 more source
Nuclear Engineering and Technology, 2021 In light of the importance of helium production in influencing the behaviour of fast reactor fuels, in this work we present a burn-up module with the objective to calculate the production of helium in both in-pile and out-of-pile conditions tracking the ...
A. Cechet +7 more
doaj +1 more source
Kinetic parameters study based on burn-up for improving the performance of research reactor equilibrium core [PDF]
Nuclear Technology and Radiation Protection, 2014 In this study kinetic parameters, effective delayed neutron fraction and prompt neutron generation time have been investigated at different burn-up stages for research reactor's equilibrium core utilizing low enriched uranium high density fuel ...
Muhammad Atta +2 more
doaj +1 more source
A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th)O2 fuels
Nuclear Engineering and Technology, 2020 The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO2 and (U, Th)O2 fuels and its impact on spent fuel characteristics was performed.
Edwin Humphrey Uguru +4 more
doaj +1 more source
Delayed fast neutron as an indicator of burn-up for nuclear fuel elements
Nuclear Engineering and Technology, 2021 Feasibility study of burn-up analysis and monitoring using delayed fast neutrons was investigated at Missouri University of Science and Technology Reactor (MSTR).
T. Akyurek, S.B. Shoaib, S. Usman
doaj +1 more source
The need for speed – Burnup determination of spent nuclear fuel
Talanta Open, 2022 Here we present the application of a novel analytical approach for high-speed evaluation of burn-up in spent nuclear fuel. This automated online separation–direct analysis method, which simultaneously measures the isotopic compositions and concentrations
Benjamin D. Roach +8 more
doaj +1 more source
FUEL BURN-UP CALCULATION FOR WORKING CORE OF THE RSG-GAS RESEARCH REACTOR AT BATAN SERPONG
Jurnal Penelitian Fisika dan Aplikasinya, 2017 The neutronic parameters are required in the safety analysis of the RSG-GAS research reactor. The RSG-GAS research reactor, MTR (Material Testing Reactor) type is used for research and also in radioisotope production.
Tukiran Surbakti, Mochammad Imron
doaj +1 more source