Using an agarose gel electrophoresis assay, single-strand breaks (ssb) induced by fission neutrons and 60Co gamma-rays in aerobic aqueous solutions of pBR322 plasmid DNA were studied. The energy-deposition events of the two radiations were characterized using a Rossi-type proportional counter to measure lineal-energy spectra. For neutrons, the dose-weighted lineal-energy mean, yD, is 63 keV micron-1--about 30 times that for gamma-rays. With increasing yD, hydroxyl radicals produced within spurs or tracks are less likely to survive due to recombination effects, resulting in decreased ssb yields. In TE buffer solution, the ssb yield induced by gamma-rays is 3.2 +/- 0.66 times that induced by neutrons at the same dose. Since the direct radiation effect is small under these conditions, we can estimate that the previously unknown G for hydroxyl radical production by fission neutrons is 0.088 mumol J-1. For glycerol concentrations that give the solution a hydroxyl radical scavenging capacity similar to that of cellular environments, the ssb yield induced by gamma-rays is about 2.0 +/- 0.24 times that induced by neutrons. Analysis shows that this trend with added scavenger is caused primarily by hydroxyl radical yields.
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http://dx.doi.org/10.1080/09553009514550851 | DOI Listing |
Entropy (Basel)
December 2024
Faculty of Physics, Warsaw University of Technology, ul. Koszykowa 75, 00-662 Warszawa, Poland.
This paper analyzes the behavior of the entropy of a nuclear fuel rod under deep burnup conditions, beyond standard operational ranges, reaching up to 60 years. The evolution of the neutron source distribution in a pressurized water reactor (PWR) fuel pin was analyzed using the Monte Carlo method and Shannon information entropy. To maintain proper statistics, a novel scaling method was developed, adjusting the neutron population based on the fission rate.
View Article and Find Full Text PDFAppl Radiat Isot
March 2025
China Institute of Atomic Energy, Beijing, 102413, China.
This paper presents a comprehensive and detailed analysis of the OECD-NEA MOX fuel benchmark based on different nuclear data libraries to investigate the reliability and accuracy of the Dragon5 lattice code developed by École Polytechnique de Montréal for the neutronic analysis of mixed uranium-plutonium oxide (MOX) fuel. The neutronics and burn-up calculations for rectangular pin and assembly geometries filled with different compositions of MOX fuel are computed. The performance of different nuclear data libraries is evaluated.
View Article and Find Full Text PDFMed Res Rev
December 2024
Sunshine Lake Pharma Co. Ltd., Dongguan, China.
Targeted charged alpha- and beta-particle therapies are currently being used in clinical radiation treatments as newly developed methods for either killing or controlling tumor cell growth. The alpha particles can be generated either through a nuclear decay reaction or in situ by a nuclear fission reaction such as the boron neutron capture reaction. Different strategies have been employed to improve the selectivity and delivery of radiation dose to tumor cells based on the source of the clinically used alpha particles.
View Article and Find Full Text PDFAppl Radiat Isot
March 2025
School of Nuclear Science and Technology, Lanzhou University, 730000, Lanzhou, China; Engineering Research Center for Neutron Application Technology, Ministry of Education, Lanzhou University, 730000, Lanzhou, China; MOE Frontiers Science Center for Rare Isotopes, Lanzhou University, Lanzhou, 730000, China. Electronic address:
In this work, the phenomenological potential-driving model based on the random neck rupture model is used to calculate and evaluate the independent yields and cumulative yields of fission products for the mass/charge distribution in the U(n, f) reaction with an incident neutron energy of 0.5 MeV and 14 MeV. In particular, the energy dependence of independent yields, including Kr, Sr, Zr, Mo, Ru, Xe, Cs, Ba and Ce, is evaluated for an incident neutron energy below 20 MeV and compared with GEFY6.
View Article and Find Full Text PDFJ Environ Radioact
December 2024
1 Kiowa Lane, White Rock, NM, 87547, USA.
Glass fragments (16 green glasses and 2 red glasses) were handpicked from crushed Trinitite. X-ray diffraction studies revealed that these samples were essentially pure glass with the exception of minor amounts (less than 4 wt%) of quartz (which acts as a diluent) in some samples. The concentrations of 45 elements in the Trinity glasses were determined using Instrumental Neutron Activation Analysis.
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