http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
Gennady N. Vlaskin,Sergey V. Bedenko,Nima Ghal-Eh,Hector R. Vega-Carrillo 한국원자력학회 2021 Nuclear Engineering and Technology Vol.53 No.12
The 13C (a,n)16O reaction cross-section is important data for nuclear physics, astrophysical, and neutrinophysics experiments, however, they exhibit uncertainties due to the discrepancies in the experimentaldata. In this study, using the Nedis-2m program code, the energy spectrum of a-induced neutrons in athin carbon target was calculated and the corresponding reaction cross-section was refined in the alphaparticle energy range of 5e8 MeV. The results were used to calculate the intensity and energy spectrumof background neutrons produced in the liquid scintillator of KamLAND. The results will be useful in avariety of astrophysical and neutrino experiments especially those based on LS or Gd-LS detectors.
Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel
Irkimbekov Ruslan А.,Surayev Artur S.,Vityuk Galina А.,Zhanbolatov Olzhas M.,Kozhabaev Zamanbek B.,Bedenko Sergey V.,Ghal-Eh Nima,Vurim Alexander D. 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.4
The fuel cycle characteristics of the IVG.1M reactor were studied within the framework of the research reactor conversion program to modernize the IVG.1M reactor. Optimum use of the nuclear fuel and reactor was achieved through routine methods which included partial fuel reloading combined with scheduled maintenance operations. Since, the additional problem in planning the fuel cycle of the IVG.1M reactor was the poisoning of the beryllium parts of the core, reflector, and control system. An assessment of the residual power and composition of spent fuel is necessary for the selection and justification of the technology for its subsequent management. Computational studies were performed using the MCNP6.1 program and the neutronics model of the IVG.1M reactor. The proposed scheme of annual partial fuel reloading allows for maintaining a high reactor reactivity margin, stabilizing it within 2–4 βeff for 20 years, and achieving a burnup of 9.9–10.8 MW × day/kg U in the steady state mode of fuel reloading. Spent fuel immediately after unloading from the reactor can be placed in a transport packaging cask for shipping or safely stored in dry storage at the research reactor site.