The ratios of the average 239 Pu and 237 Np fission cross-sections to the average 235 U fission crosssection were determined experimentally. Experiments with U-assembly QUINTA were carried out using the accelerator complex "Nuclotron" of the Veksler and Baldin Laboratory of High Energy Physics (VBHEP) of the Joint Institute for Nuclear Research (JINR) (Dubna, Russia). Experiments were conducted in the frame of the project "E&T RAW". It is based on so called Relativistic Nuclear Technology (RNT) proposed recently [1] by one of the institutions (CPTP "Atomenergomash", Moscow) participating in "E&T RAW" collaboration. The assembly was irradiated by deuterons and carbon ions with energies 2 and 4 GeV/A. Comparison between experimental results and MCNPX calculations are presented. Accumulation and burning of plutonium, neptunium and others isotopes influences the neutron balance of the assembly that attracts an interest in such measurements.
In 2011-2017 in the framework of the international collaboration project “Energy and Transmutation of RAW”, a series of experimental studies on the deep subcritical uranium assembly QUINTA were carried out. The massive uranium target (512 kg of natU) was irradiated with 0.66 GeV proton, deuterons and 12C nuclei (1 to 4 AGeV) from the Phasotron and Nuclotron accelerators (JINR, Dubna). The main results of experimental studies carried out with the participation of the Kharkov group of collaboration are presented.
Simulation of a ~21 t depleted uranium target irradiated by 1…10 GeV proton and deuteron particles with the help of FLUKA simulation package was carried out. Neutron spectra and neutron flux in a target volume were obtained. Total number of 235U (n,f), 238U(n,f) reactions occurred in a target were determined. Beam particle power multiplication are calculated. The calculations were performed for the purpose of planning experiments on irradiation of a uranium target (22 tons of depleted uranium) at JINR (Dubna) within the framework of the international project “Energy and Transmutation of RAW”.
The results of a study on the choice of the optimal measurement geometry, measuring capacity and method of sealing the measuring capacity for determining the concentration of radon-222 in samples of mineral radon water are presented. Studies of radon water samples were carried out in laboratory conditions on a stationary gamma spectrometer based on a semiconductor Ge(Li) detector. The concentration measurements in the samples were carried out in accordance with MVI. MN 3421-2010 “Methodology for measuring the volumetric and concentration of gamma-emitting radionuclides on gamma spectrometers with semiconductor detectors” for standard plastic vessels “Denta, 0.1 l” and “Marinelli, 1 l”, and glass containers with a volume of 0.5 l with lids for twisting and seaming. The results of the research showed that the leakage of radon from a glass container with a metal lid for sealing is minimal. This method of sampling and sealing the measuring vessel makes it possible to increase the accuracy of the presented measurement results by reducing the corrections for sample preparation when calculating the expanded measurement uncertainty. A glass container with a volume of 0.5 l with a metal cap for seaming was used to measure the concentration of radon in samples of mineral radon water taken from wells and a drinking fountain of the Radon sanatorium of Belagrozdravnitsa JSC (Dyatlovo District, Grodno Region). The concentration range was 760–2100 Bq/kg. The selected measuring container, the method of its sealing and the measurement geometry can be used for future measurements of the radon concentration in samples of mineral radon water taken in the sanatoriums of the Republic of Belarus.
Simulation of a quasi-infinite uranium target irradiated by 1 GeV proton and deuteron particles with the help of FLUKA simulation package was carried out. Neutron spectra and neutron flux in a target volume were obtained. 235U(n,f), 238U(n,f), 238U(n,g) reaction rates in a target were determined. Beam particle power multiplication were calculated.
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